Text

Final Radiological Survey Performed at Ga Bldg 27 (EA-1)
	ML20155K422
Person / Time
Site:	07000734
Issue date:	11/02/1998
From:	Finchum S, Gonzales L, Joseph Turner; GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:	;
Shared Package
ML20155K414	List: ML20155K411; ML20155K416; ML20155K422;
References
	NUDOCS 9811130235
	Download: ML20155K422 (112)
	v • d • e

{{#Wiki_filter:- - _ _ _ _ - 1 FINAL RADIOLOGICAL SURVEY PERFORMED AT GENERAL ATOMICS' BUILDING 27 (EA-1) I I I I I I Prepared By: John Turner, Laura Gonzales, Stephen Finchum, Richard Stowell, Cornelius Stanley, Barbara Lyons and l Dane McKay November 2,1998 [ B PDR11

-. ~. i Table of Contents INTROD U CTI ON......,..................................................... 1 S ITE DESC RIPTI ON......................................................... 1 PREVIOUS ACTIVITIES (HISTORY OF USE).................................... 2 CRITERIA FOR RELEASE TO UNRESTRICTED USE............................. 2 Facilities and Equipment................................................. 2 Exposure Rate Guideline................................................. 3 Soil Release Criteria.................................................... 3 IN STRUM ENTATION........................................................ 3 - B ACKGROUND MEASUREMENTS............................................ 3 Instrument Background Measurements..................................... 3 Background Soil Concentrations........................................... 4 Exposure Rate Background............................................... 4 DECONTAMINATION ACTIVITIES............................................ 5 Removal ofItems and Equipment from Laboratories........................... 5 - General Decontamination Procedures....................................... 5 FIN AL SURVEY PL ANS...................................................... 6 Objectives and Responsibilities ...........................................6 Classification of Areas ..................................................6 Surveys Performed..................................................... 7 SURVEYING AND SAMPLING OF TRENCHES.................................. 7 Description of the Trenches ..............................................7 Removal of Equipment from the Trenches..................................., 7 Soil / Debris Removed from the Trench (8 samples)............................ 8 Pipe S amples.......................................................... 8 Soil Remaining in Trench................................................ 9 SOILS SAMPLES FROM UNDERNEATH THE CONCRETE SLAB.................. 9 Soil S am ples......................................................... 10 Sample Preparation and Counting........................................ 10 RELEASE OF THE METAL ROOF TO UNRESTRICTED USE..................... 10 S U RVEY S U M M ARY........................................................ I 1 RES ULTS OF FINAL SURVEYS.............................................. 11 S cannin g............................................................ 1 1 Fixed Measurements.................................................... I 1 Removable Contamination Surveys........................................ 12 Paint Sampling .......................................................12 Exposure Rate Measurements............................................ 12 GA INTERNAL CONFIRMATORY SURVEY.................................... 13 l S urvey P l an.......................................................... 13 - Results of the GA Confirmatory Survey.................................... 13 C ONC LU SI ON............................................................. 14 y e I

L List of Tables Table 1: USNRC's Acceptable Surface Contamination Levels....................... 15 Table 2: State of CA Acceptable Surface Contamination Levels..................... 16 Table 3: List of Instruments.................................................. 17 Table 4: Background Measurements (Obtained from Building 13).................... 21 j Table 5: Results of Final Surveys in Building 27................................. 24 Table 6: Results of Final Soil Samples Collected in Building 27..................... 28 Table 7: Internal GA Confirmatory Surveys in Building 27......................... 32 Table 8: Results of Soil Samples Collected from Building 27 During Internal GA Confirmatory Survey................................................ 3 3 Table 9: Background Soil Sample Results....................................... 34 I At of Fieures (unpaged) Figure 1: Plan View of General Atomics Site Figure 2: Building 27 and 21 in Relation to Surrounding Facilities Figure 3: Building 27 Prior to Modifications Figure 4: Building 27 Current Status Figure 5: Affected & Unaffected Alpha and Beta Floor and Outside Sidewalk Scan Results Figure 6: Affected & Unaffected Alpha and Beta Wall Scan Results Figure 7: Unaffected Alpha and Beta Wall Scan and Exposure Rate Measurements Results Figure 8: Affected Floor and Walls Fixed and Removable Contamination Results i Figure 9: Unaffected Fixed and Removable Contamination Results Figure 10: Exposure Rate Measurements and Paint Sample Results Figure 11: Sidewalk. Fixed, Removable Contamination and Exposure Rate Measurements ' Figure 12: A/C and Heating Duct work Fixed and Removable Contamination Results Figure 13: Sprinkler System. Removable Contamination Results Figure 14: Overhead "I" Beams and Lights. Fixed and Removable Contamination Locations Figure 15: South Trench " Fill Soil" and Trench Dirt / Debris Collection Locations Figure 16: Soil Sample Collection Locations Figure 17: Trench. Scan and Fixed Measurements Figure 18: Trench. Removable Contamination Results APPENDIX A: Process Knowledge Report for the EAl (Bldg. 27) Laboratories APPENDIX B: Building 27 Final Survey Plans APPENDIX C: Revised Final Trench Survey and Soil Sampling Plan for Building 27 (EA-1) l

l l l Table of Contents - INTRODUCTI ON............................................................ 1 SITE DESC RIPTION......................................................... 1 PREVIOUS ACTIVITIES (HISTORY OF USE).................................... 2 CRITERIA FOR RELEASE TO UNRESTRICTED USE............................. 2 Facilities and Equipment................................................. 2 Exposure Rate Guideline................................................. 3 l Soil Release Criteria.................................................... 3 IN STRUMENTATION........................................................ 3 B ACKGROUND MEASUREMENTS............................................ 3 l Instrument Background Measurements..................................... 3 Background Soil Concentrations........................................... 4 Exposure Rate Background............................................... 4 DECONTAMINATION ACTIVITIES........................................... '. 5 Removal ofItems and Equipment from Laboratories........................... 5 l General Decontamination Procedures....................................... 5 FINAL S URVEY PLAN S...................................................... 6 Objectives and Responsibilities ...........................................6 Classification of Areas ..................................................6 S urveys Performed..................................................... 7 SURVEYING AND SAMPLING OF TRENCHES.................................. 7 Description of the Trenches ..............................................7 Removal of Equipment from the Trenches................................... 7 Sand / Debris Removed from the Trench..................................... 8 P i pe S ampl es.......................................................... 8 Soil Remaining in Trench................................................ 9 SOILS SAMPLES FROM UNDERNEATH THE CONCRETE SLAB.................. 9 S oil S ampl es......................................................... 10 Sample Preparation and Counting ........................................10 RELEASE OF THE METAL ROOF TO UNRESTRICTED USE..................... 10 SU RV EY S U MMA RY....................................................... 1 1 RESULTS OF FINAL SURVEYS.............................................. 11 S cannin g.............................................................. I 1 L Fixed Measurements.................................................... I 1 Removable Contamination Surveys........................................ 12 Paint S amplin g....................................................... 12 l Exposure Rate Measurements............................................ 12 GA INTERNAL CONFIRMATORY SURVEY.................................... 13 L - S urvey Pl an......................................................... 13 l Results of the GA Confirmatory Survey.................................... 13 L CONC LUS I ON............................................................. 14 (

Building 27 Final Radiological Survey Report 4 ammmmasmemmes Introduction General Atomics is continuing its efforts directed at decontaminating, as appropriate, and obtaining the release to unrestricted use of selected facilities at General Atomics GA has recently completed the Final Radiological Survey of Building 27, also known as the Experimental Area-1 or EA-1. GA is requesting both the State of California and the Nuclear Regulatory Commission (NRC) to release Building 27 to unrestricted use. The total area to be released to unrestricted use is ~6500 ft2 2 (~604 m ). This report documents the results of extensive and comprehensive radiological measurements completed inside Building 27 and the surrounding outside sidewalk area (" footprint") around the building and demonstrates that these areas meet the approved criteria for release to unrestricted use. Site Description A plan view of the GA Site is shown in Figure 1. The location of Building 27 in relation to other facilities on GA's Main Site is shown in Figure 2. Building 27 as it existed prior to decommissioning is shown in Figure 3. Building 27 and the surrounding " footprint" to be released to unrestricted use is shown in Figure 4. The building was constructed between 1964 and 1965 on a site adjacent to, and immediately west of, the TRIGA* Reactor Facility (Building 21); see Figures I and 2. The building is of concrete masonry construction, with exterior dimensions of 41.3 ft x i12 A (~ 4625 ft ) or 12.6 m x 34.1 m (~ 430 m ). 2 2 The building encompasses an interior space of approximately 4400 R2 (~ 405 m ). The building was 2 designed as a rectangular open shell with no internal load bearing walls. The only permanent interior concrete block walls enclose the small Mechanical Service Room located near the center of the building's east wall. The building's concrete floor incorporates a sub-floor service (utility) trench, ~ 2 feet wide by 3 feet in depth (~ 0.61 m x 0.91 m). This central service trench is oriented along the buildings north-south axis. The central trench accommodated installed service plumbing (i.e., supply lines for domestic water, deionized water, natural gas and compressed air). The trenches also contained drainage lines routed to the sanitary sewage system and segregated lines routed to the radioactive liquid waste tank, located northeast of the adjacent EA-1 Bunker (Building 27-1). The total area to be released to unrestricted use is ~6500 n2, comprised of ~4625 ft of building and 2 ~1875 R2 of sidewalk around the building. 1

l l Building 27 Final Radiological Survey Report 4 cumuurma nranmes Previous Activities (History of Use) Building 27 previously housed radiochemistry and analytical chemistry laboratories and ofDees. The laboratories included a gamma spectrometry lab, a physical testing lab, a chemical storage room, an emission spectrometry laboratory, a liquid chromatography lab, a combustion lab, and a sample preparation lab. Operations in these labs ceased circa September 1996. Equipment and material removal and disposition commenced soon aller, A detailed description of the site and its history is provided in Appendix A:" Process Knowledge Report for the EAl (Bigd. 27) Laboratories." Criteria for Release to Unrestricted Use Facilities and Eauioment U.S. NRC's criteria for releasing facilities and equipment to unrestricted use is shown in Table 1. The State of California's guidelines,"DHS Criteria for Release of Facilities and Equipment to Unrestricted Use," also known as "DECON-1,"is shown in Table 2. Based on the previous history of work conducted in the laboratories and the results of surveys and samples, the predominant radiological contaminants were determined to be Cs-137 and Co-60. The approved guideline values for release to unrestricted use for these beta / gamma emitters are provided below: 2 2 5,000 dpnV100 cm (averaged over a 1 m area) 2 2 2 15,000 dpm/100 cm (maximum in a 100 cm area if the average over 1 m is met) 2 1000 dpm/100 cm (removable activity) Following aggressive decontamination of the concrete surface, many samples of concrete and debris were collected and analyzed. Only Cs-137 and Co-60 were detected. However, one sample showed elevated beta activity above expected values. This could be due to Sr-90 since it was used in the laboratories. Because of this, GA made a reasonable effort to remove residual contamination to levels below the guidelines for Sr-90 as follows: 2 2 1,000 dpm/100 cm (averaged over a 1 m area) 2 2 2 3,000 dpm/100 cm (maximum in a 100 cm area if the average over 1 m is met) 2 200 dpm/100 cm (removable contamination) However, since it is known that Cs-137 is the predominant contaminant, the actual release criteria forfacility surfaces, considering an equal contribution of beta / gamma emitters (Cs-137 and Co-60) and Sr-90 activity (a conservative assumption) is: 2 i I

l Building 27 Final Radiological Survey Report 4 cume== mranses l l 3,000 dpm/100 cm (averaged over 1 m area) 2 2 l 9,000 dpm/100 cm (maximum in a 100 cm area if the average over 1 m is met) 2 2 2 2 600 dpm/100 cm (removable contamination) Exoosure Rate Guideline The guideline value for exposure rates measured at 1 m above the surface, is 10 uR/hr above background levels. Soil Release Criteria The predominant radionuclides found in soil at GA and the soil release criteria (above background concentrations) in pCi/g for these radionuclides is provided below: Cs-137 15 pCi/g Co-60 8 pCi/g Thorium (Th-228 + Th-232) 10 pCi/g Enriched Uranium (U-234 + U-235) 30 pCi/g Depleted Uranium 35 pCi/g If more than one radionuclide exists, the sum of the fractions of the concentrations is calculated as follows: C [" d<1 c., L, The average soil concentration of radionuclide 1. C, = L, The maximum soil limit for f (pCi/g). = Instrumentation A list ofinstruments used during the radiological surveys is shown in Table 3. The table includes:(1) a description of the instrument, model number and its serial number, (2) a description of the detector (if applicable) and its serial number, (3) instrument ranges, (4) calibration due dates, (5) typical background readings and (6) calibration efficiencies (if applicable). All of the instruments used were calibrated semiannually and after repair except for exposure rate meters which were calibrated quarterly. Background Measurements Backcround Measurements for Instruments / Detectors i Building 13 on GA's main site was used for conducting background measurements on instruments used for the final survey because: (1) there is no history involving radioactive materials or storage of j 3 i l

Building 27 Final Radiological Survey Report 4 - = mrammes radioactive materials in Building 13,(2) the various surfaces found in Building 27 could also be found in Building 13 and (3) the age of the building closely approximates the age of Building 27. For the fixed background measurements, shown in Table 4, the mean and standard deviation for each 2 surface surveyed with the 100 cm gas flow proportional detector were calculated using equations 8-11 and 8-12 from the draft version of NUREG/CR-5849' as shown below: Equation (8-11) i=M,".',x, O s Equation (8-12) g,, (i-x,) ') n -1 Minimum detectable activities (MDA's) for each type of surface (see Table 4), were calculated using equation (5-2) from the NUREG/CR-5849 as shown below: Equation (5-2) 2.71 +4.65/B,xt 2 MDA= (dpm/100cm ) ^ txEx 100 Where: B = background rate (cpm) a t = count time (min) E = efliciency 2 A = area cf the detector (cm ) Background Soil Concentrations Typical background concentrations measured by gamma spectroscopy in soil near the GA site have been established (at the 95% confidence level) and are provided in Table 9 along with the locations where these samples were taken. Exoosure Rate Background Typical exposure rate background for this site is about 15 R/hr measured at I m from the surface. This value can be measured south of Building 15 (an office building on the eastem portion of the GA site). Measurements taken offsite in 10 different locations over a period of a year also give an average ' Manual for Conducting Radiological Surveys in Support of License Termination (Draft for Comment), NUREG/CR-5849, ORAU-92/CS7, Oak Ridge Associated Universities. June 1992. 4

Building 27 Final Radiological Survey Report 4 - = meness of about 15 R/hr (measured at I m from the surface). Normal background exposure rates increase to about 22 R/hr at 1 m from the surface in small rooms with concrete floors and walls and up to 28 R/hr inside concrete lined trenches or concrete lined pits (background measurements inside a concrete pit near Building 2 confirm this). Decontamination Activities Removal ofitems and Eauinment from Laboratories All of the laboratory and office items (i.e., equipment, supplies, furniture, etc.) and various other materials contained within the building have been removed. These items and equipment were surveyed and released to unrestricted use or properly packaged and disposed of as radioactive waste . following routine Health Physics procedures. All of the non-load bearing walls were also surveyed and removed to create one large open room within the main building area and the unaffected office area (see Figure 4). The mechanical room remains as a separate room since it was enclosed by concrete block walls. All of the tile was removed resulting in a concrete surface throughout the entire inside of the building. ) General Decontamination Procedures Contaminstion above the release criteria was detected on the concrete floors, on 2 metal plates covering the trenches and in a section of concrete lined trench. In addition, contamination was found on the lower portions (generally below 2 m) of the laboratory walls and on the overhead ducts. The lower portion of the interior west wall (grids 18-F thru 36-F) was removed and the area aggressively decontaminated. The lower portion (~ % m) of the west wall (grids 22-F thru 25-F) was removed and replaced with plywood. The support foundations (footings) at grids 21-F and 25-F were also removed and reconstructed with concrete after documented surveys confirmed that radiation levels were below the release criteria. Decontamination activities were performed in accordance with an approved Radiological Work l. Authorization (WA) and/or Radiation Work Permit in accordance with GA's Radioactive Material I License and GA's Site Decommissioning Plan. The WA included procedures for decontamination of various surfaces. In general, remediation of contaminated areas was accomplished using the following methods: (1) Vacuuming using a HEPA filtered vacuum cleaner. (2) Wiping with cloths or masslin cloths. (3) Scrubbing with a metal brush or scraping with a metal chisel. ' (4) ~ Scabbling with a needle gun or metal grinder. .(5) Use of a jack-hammer & pneumatic chisel. (6) Use of a blastrac unit for abrasive cleaning & removal of the contaminated concrete from the floors. - Decontamination was accomplished on the concrete floor mainly by using a blastrac unit which uses metal shot to blast (abrade) the concrete surface. The amount of concrete removed at any one time i 1 5 ?

Building 27 Final Radiological Survey Report 4-= mances was determined by the speed that the blastrac equipment was moved across the floor. The slower the blastrac was moved across the floor the more abraded material (concrete) that was removed. A jack hammer and needle gun were used in areas where the blastrac unit could not reach or was ineffective (e.g., did not go deep enough). Other locations (walls and concrete lined trenches) were aggressively decontaminated by vacuuming, scraping, using a heat gun, a needle gun, and/or ajack hammer. Final Survey Plans Obiectives and Resnonsibilities The objectives of the final survey plan were (1) to demonstrate that the average surface contamination levels for each survey unit were within the authorized value, (2) to show that the maximum residual activity (" hot spot" area) did not exceed three times the average value in an area up to 100 cm, (3) 2 that a reasonable effort was made to clean removable contamination and fixed contamination and (4) that the exposure rates in occupiable locations are less than 10 R/hr above background measured at I meter above the surface. Surveys were taken only by qualified Health Physics Technicians having a minimum of three years Health Physics experience in accordance with approved Survey Plans. Samples were counted in GA's Health Physics Laboratory which maintains an effective QA program. Classification of Areas Each of the laboratories and the hallway between these laboratories were classified as " suspect affected areas." The office areas and the outside walkways (footprint) were classified as " unaffected areas"(see Figure 4). The service trench and the concrete excavations (portions of the concrete floor removed for soil sampling) were classified as "non-suspect affected areas." (The concrete lined trench was re-classified as an "affected area" after contamination was detected in a portion of the trench). ' Suspect Afected Area: Former laboratories' 101,101 A,101 B,102,106,107,108,109, i 10,111, l~ l 12,113,114, i 15,116 and all of the hallway (except the small portion of the hallway in the L unaffected area); see Figure 3. All intemal walls were removed. The affected area is now an open l area (see Figure 4). Non-Suspect Afected Area: The concrete lined service trench and the trenches created after the removal of the radioactive underground drain line as well as the soil beneath the building were classified as "non-suspect affected areas." Nolt This trench was re-classified as an "affected area" l after contamination was found during the final survey and surveyed accordingly. l- . Unagected Areas: Rooms 100,103,104,105A,105B, the mechanical room, the outside walkway around the building and the small portion of the hallway mentioned above (see Figure 3). The internal walls of the office area were also removed (see Figure 4 for details). t 4 6 4 l r-, ~.n., +,, ,s,_. ,,c-, -,+ ~

l Building 27 Final Radiological Survey Report 4 summmm.nmuses l Surveys Performed l Survey plans were developed based on the previous history of the building, the radionuclides of concern, the various types of surfaces, the potential for contamination, the classification of the area l (suspect afrected, non-suspect affected or unaffected) and the results of the surveys during and after decontamination. These surveys were completed in accordance with approved written Final Survey Plans. Copies of these (latest version) are provided in Appendix B " Revised Building 27 Final Survey Plan," dated j May 7,1998, and Appendix C," Revised Final Trench Survey and Soil Sampling Plan #1 for Buildmg 27 (EA-1)," dated May 15,1998. These surveys included scanning of the floor and wall surfaces of l the building and sidewalk surrounding the building. The surveys also included the collection and analyses (by gross alpha / beta counting) of smears, taking fixed measurements, exposure rate measurements (uR/hr) and sampling (i.e., soil, sand / debris, paint, and concrete). Surveying and Sampling of the Trenches Description of the Trenches The building's concrete floor incorporates a sub-floor service (utility) trench,- 2 feet wide by 3 feet in depth (~ 0.61 m x 0.91 m). This central service trench is oriented along the buildings north-south j axis. The central trench accommodated installed service plumbing (i.e., supply lines for domestic water, deionized water, natural gas and compressed air). The trenches also contained drainage lines routed to the sanitary sewage system and segregated lines routed to a radioactive liquid waste tank, located northeast of the adjacent EA-1 Bunker (Building 27-I bunker). This tank is no longer used but is still in place and will be removed and decommissioned with the EA-1 bunker facility. The central service trench was crossed by one radioactive drain line (routed from room 27/109 to room 27/108). In addition, the radioactive drain line serving the sink in room 27/l16 was routed through the central service trench from the northem trench terminus to room 27/108. The trenches are for the most part concrete lined with the exception of the trench that housed the main underground radioactive drain line. However, the drain pipe was encased in concrete. Removal of Eauioment from the Trenches All radioactive drain lines from the laboratories and the main radioactive drain line which exists the building to the west, were removed and properly packaged and disposed of as radioactive waste. The soil in the trench formed as a result of the removal of this drain line was sampled along the sides and bottom inside the building. The other utility pipes (i.e., domestic water, deionized water, natural gas, and sanitary sewage lines) were left in place, in addition, the trenches (~3' deep) contained debris / sand / soil along the bottom of the trench. The south end of the trench was (and still is) completely filled with " fill" soil, i 7

Building 27 Final Radiological Survey Report

j* amp=== mrummes The initial survey plan for the concrete lined trenches required surveying about 10% of the concrete surface (initially the trenches were classined as "non-suspect affected area") and the collection of debris / soil from the bottom of the trenches. The results of this survey showed that a portion of the trench was contaminated. As a result, the area was re-classiGed as an " suspect affected area" which required 100% survey coverage. In order to allow access to scan 100% of the trench, the utility lines and pipes which ran through the trenches were removed.

Sand / Debris Removed from Trench [ Eight (8) sand / debris samples were collected from the bottom of the concrete lined service trench and were analyzed by gamma spectroscopy. Three (3) of the eight (8) results showed Cs-137 and Co-60 activity, but the levels were well below the release criteria. However, it was decided to dispose of this soil as radioactive waste. All sand / debris was removed from the trenches with the exception of the southern end of the trench. The last 25' of the southern end of the trench was filled at some time in the past with "Hil" soil. After the debris / soil was removed from the majority of the trench, GA cleaned (by vacuuming) the bottom of the service trench. The concrete surfaces were surveyed and areas found to be above the release criteria were decontaminated to levels below the release criteria. Pine Samples The sub-Hoor service (utility) concrete lined trench is oriented along the buildings north-south axis. All drain lines and other utility lines were removed with the exception of 2 previous /v abandoned Pl%t These two pipes (called the " east drain line" and " west drain line") are located in the southern portion of the trench and remain underneath "Sil" soil. These pipes were removed up to a point ~25' from the south wall. The east drain line is a sanitary (waste) drain line thatjoins the main sewer line within several feet ofleaving the south end of the building. The west drain line was previously a radioactive waste drain line thatjoined the centrally located radioactive drain line which went to the liquid waste storage tar.k. The west drain line is capped (plugged off) outside the southern portion of the building. A sample (debris / scale) was collected from the inside of each drain pipe, at the location ~25' from the south wall where the pipes had been previously cut off. At this location, the pipes are about to be covered with "Sil" soil. The gamma spectroscopy results showed traces of contaminants (see table below) but the levels were very low and well below GA's release criteria. The pipes were also checked with hand-held alpha and beta / gamma detectors and no contamination was detected. Although the results showed trace contaminants (see table below), Hve (5) drums of"Hil" soil were removed to allow access and sampling from inside the pipes at the south wall. These results showed even lower concentrations of Cs 137 and Co-60 (see table below). l i 8 i

Building 27 Final Radiological Survev Report

l* cammmm manmes Results of Samples Collected Inside Existing Drain Pipes in Trench Radionuclide Concentration (pCi/g) l Pipe Pipe Location Cs-137 Co-60 U-235 At end inside building ~25' O.45
7 %

0.14 21 % 0.11 102 % l West Pipe from south wall At south wall 0.26 20% <0.1 < 0.2 At end inside building -25' O.42

18 %

0.04

76 %

< 0.2 East Pipe from south wall At south wall 0.07

23 %

0.07 30% 0.13

58 %

The concrete sidewalk and soil outside the southern portion of the building were excavated in order to I expose the pipes for further investigation. A soil sample was taken of the excavated soil at this location and results showed only background levels of radioactivity. I Based on the results and consideration for the large volume of soil that would have to be removed to gain access to the entire 25' of pipe, the two pipes were left in place. The Gye drums of soil removed to allow Health Physics to sample the two abandoned drain lines y located under the Gli soil were also sampled. Gamma spectroscopy results showed only natural background levels of activity except for one sample which showed Cs-137 in trace quantities (~0.02 I pCi/g 70%). The soil was not put back into the trenches and is currently being stored in the 5 drums awaiting proper disposition. I Soil Remaining in Trench Twelve soil samples ("Gil" material), were collected from the soil remaining in the south trench. This soil completely fills the trench from the bottom to the top (about 3' deep). Two of these samples were l taken at sub-surface levels ( ~ 32" below the top of the "Dil" soil) and one sample was taken at ~ 24" I below the concrete floor surface level. l All sample results were at or near natural background soil levels, except for one of those collected at I the 32" sub-surface level which showed trace levels of Cs-137 and Co-60 contamination, however, the levels were well below the soil release criteria. The results of the twelve samples (S-32 through S-43) are provided in Table 6 and the locations where the samples were taken are shown in Figure 15. Soil Samples from Underneath the Concrete Slab Concrete floor sections were cut and removed in order to sample the soil undemeath the building, in addition, soil samples were taken from inside the trench (along the sides and the bottom of the trench) which previously housed the main radioactive waste drain line (not concrete lined) and from areas 9 u e

[ Building 27 Final Radiological Survey Ret) ort 4-= mrammes within the facility where decontamination (i.e., jack-hammering) was deep to access the soil for sampling. Soil Samnles Collected Twenty-eight (28) surface (0-6") soil samples and 5 subsurface samples (6-12") were collected underneath the concrete slab in biased and random locations throughout the inside of the building. Expansionjoints between the slabs of concrete flooring were especially targeted for sampling, due to i the ease ofliquids to flow between these separations to the soil below. A few of these sample results showed trace quantities of U-235, Cs-137 and Co-60 but all results were significantly below GA's release criteria. Gamma spectroscopy results may be found in Table 6 (S-1 through S-29) and locations in Figure 16. Two soil samples S-30 and S-31 were taken at grid locations J-22 and J-23 respectively, where ) l aggressive decontamination using ajack-hammer had been conducted on the concrete surface. Both sample results were at or near background levels (see Table 6 for results and Figure 16 for locations). Sample Prenaration and Counting Each of these samples were properly logged, labeled, packaged and tracked. Samples were dried, placed into a marinelli beaker, weighed and counted by gamma spectroscopy, All samples were analyzed in GA's Health Physics Laboratory with a Canberra Low Sensitivity Gamma Spectroscopy MCA System using a high purity Germanium Detector. The system is calibrated using NIST traceable standards and performance checked daily. Samples were counted for a minimum of 30 minutes each. A 30 minute count is sufficient to detect the radionuclides ofinterest (Cs-137, Co-60, U-235, U-238 and thorium daughters) at levels well below GA's approved release criteria. Release of the Metal Roof to Unrestricted Use The HEPA units on the roof with associated equipment (i.e., plenums, filters, inlet and outlet ducting, blowers, electric motors and exhaust piping) were removed. The plenums, HEPA filters and inlet l ducting were properly packaged and disposed of as radioactive waste. Inside the building, the flex-l metal HEPA intet ducts were also removed, properly packaged and disposed of as radioactive waste. The corrugated, galvanized metal roof was overlaid with a 1.5 inch layer of gravel, a 1.0 inch layer of l tar paper, a 1.0 inch layer ofinsulation and a layer of heavy black plastic sheeting. Samples of gravel, I tar / insulation were collected and analyzed by gamma spectroscopy. Based on the results, the material will either be disposed of as radioactive waste or segregated for release to unrestricted use at a later date. After the roofing materials were removed from the building, the remaining corrugated, galvanized metal roof and the remaining metal HEPA system enclosure (barrier) were surveyed in order to ensure that the radiological conditions satisfy the NRC and State of CA guidelines for release to unrestricted 10 l l l-

f Building 27 Final Radiological Survev Report 4 cassummanraumes l use. A Final Survey Report and letter requesting release of the roof to unrestricted use was submitted to the NRC and the State of CA on August 25,1998. The State of CA performed confirmatory surveys on the exposed metal roof on August 27,1998 and August 28,1998 and informed the NRC of the results. Both the NRC and the State of CA have released the metal roof to unrestricted use. Survey Summary A summary of the number of fixed measurements, smears, exposure rate measurements (uR/hr), and samples taken is provided below: - Building 27 Survey Summary Survey

of Fixed
of
of Exposure Rate
of Soil,
of Paint Measuremen.m Smears Measurements Sand,or Samples

( R/hr) - Debris Samples l Final Survey 308 231 133 47 12 GA Intemal 45 35 136 5 Confirmatory Total 353 266 269 52 12 Results of the Final Surveys After decontamination and post decontamination surveys were complete, GA began the final survey. The re ilts are provided in Tables 5 and 6 and Figures 5 through 18. Scanning 2 Scans with the 434 cm gas-Dow proportional detectors (Hoor monitors) were conducted in order to identify elevated areas of activity. Areas with elevated readings were further investigated with either 2 the 100 cm (D) Eas-Dow proportional detectors or hand held (a or p) instruments / detectors to determine if the levels were above the release criteria. Investigation of these areas showed that no further decontamination was needed (113 e f the highest reading grid blocks were checked and the 2 maximum activity was 599 dpm/100 cm ). The results of these scans are provided in Table 6 and in the respective figure for each location. Fixed Measurements A total of 308 fixed measurements were performed during the final survey in the affected and unaffected area Coors and walls, overhead structures,1 beams and lights, inside the concrete lined trench, and the concrete sidewalk around the building. The measurements were taken using a beta l gas-proportional counter having a 100 cm detector. 2 ( l1

Building 27 Final Radiological Survey Report 4 - = mronnes Two (2) minute fixed measurements were taken. An appropriate background was determined for each type of surface and subtracted from the survey readings. The readings were converted from 2 cpm to dpm/100 cm using the appropriate count time, the efficiency of the detector and the geometry of the detector. The results are provided in Table 5 and the approximate locations (and i results) are shown in their respective figures. All results were < 1000 dpm/100 cm after 2 decontamination. l Removable Contamination Surveys Removable contamination measurements (smears) were performed on all surfaces including the

floors, walls, overhead structures (light fixtures, I-beams, fire sprinkler system and the heating and A/C duct work), inside the service trench and on the sidewalk surrounding the building. A total of 231 smears were taken during the final survey.

Smears consisted of using a Whatman Filter Paper (4.7 cm diameter) and wiping an area of-100 2 2 cm. The smears were counted in GA's Health Physics Laboratory using a Canberra 2400 low level alpha / beta cc inting system. The maximum smear result in dpm/100 cm for both alpha and beta are 2 provided ir. able 5 and shown in their respective figures. The maximum smear results were < 90 2 2 dpm/100 ( t and < 41 dpm/100 cm p; well below the release criteria of 600 dpm/100 cm, Paint Samf 4 A total of 12 paint samples were collected in the affected area of Building 27. At each location where a paint sample was collected, a 2 minute fixed measurement was taken before and after paint removal. The highest fixed measurement result (taken after paint was removed at location 11 shown 2 on Figure 10) was 290 dpm/100 cm ; well below the release criteria. The paint samples were analyzed by gross alpha / beta counting. The highest result (also at location 2 2 i1 shown on Figure 10) measured 251 dpm/100 cm beta and < 10 dpm/100 cm alpha, also below the release criteria. Exnosure Rate Measurements Direct radiation exposure rate measurements (133) were taken at various locations inside the facility, the surrounding sidewalk and inside the service trench. The measurements were taken at ~1 meter above the surface using a microR meter. Measurements inside the facility ranged from 15-19 R/hr after decontamination was completed. Measurements on the sidewalk surrounding the building ranged from 14-21 R/hr(they were slightly elevated due to storage of radioactive material at the TRIGA' Reactor (Building 21) and Hot Cell (Building 23) facilities nearby. Inside the concrete lined service trench, on contact with the concrete in the bottom of the trench, l levels measured as high as 28 R/hr after decontamination. This is due to measurements being taken inside the trench at a depth of ~ 2.5' deep (normal background levels under these conditions). The 12 i

i Building 27 Final Radiological Survev Report 4 cup- - manmes results are provided in Table 5 and the approximate locations (and results) are shown in their respective figures. l GA Internal Confirmatory Survev Survey Plan GA conducted an internal Confirmatory Survey to ensure that results of the Final Survey are indeed below the State of Califomia release criteria. This survey was performed in accordance with a written plan by Health Physics Technicians not assigned to perform the Final Survey, i.e., an independent survey. The plan required the following surveys: SuspectAfectedArea: Scan ~25% (p/y) on the concrete floor surface and 10% p/y of the concrete block walls (below 2 m). Take fifteen (15) fixed measurements on the concrete floor surface. Take three (3) fixed measurements each on the west and east walls and two (2) each on the north and 2 south walls (below 2 m). Take five (5) 100 cm smears on the floor,10 on overheads,10 on I-beams and 10 in miscellaneous areas of the building. Take exposure rate measurements in (uR/hr) at 1 meter from the surface ~ l every 2 meters. Surveys in trenches: Take ten (10) fixed measurements in the trench and concrete excavations (include 3 in grids J, K, L, M 20 to 23). Take five (5) random soil samples (include a sample from the former radioactive drain line trench). Scan tormer radioactive drain line trench with a microR meter. UnaffectedArea: Offices: Scan ~10% p/y of the concrete floor and take four (4) fixed measurements. Take exposure rate measurements in (uR/hr) at I meter from the surface every 3 meters. Sidewalk: Scan ~10% p/y of the concrete sidewalk around the building and take two (2) fixed measurements each on the west and east sidewalk and one each on the south and north sidewalk. Take exposure nte measurements in (yR/hr) at I meter from the surface every 3 meters. Results of the Internal GA Confirmatory Survey During scanning, elevated rndings were found on the west wall, inside the service trench, the window frames and overhead duct work (including the insulation). Although the levels were below 2 2 the release criteria of 3000 dpm/100 cm (averaged over 1 m ); these areas were decontaminated. A total of 45 (1 minute) fixed measurements were taken. All readings were below the release criteria 2 2 of 3000 dpm/100 cm ; the highest result was 968 dpm/100 cm. 2 A total of 35 smears were collected; results were < 10 dpm/100 cm alpha activity and < 17 dpm/100 2 2 cm for beta activity; well below the release criteria of 600 dpm/100 cm, A total of 136 exposure rate measurements were taken; values ranged from 12-21 R/hr. The readings were slightly elevated on the northeast side of the building due to Building 27's proximity to the TRIGA* Reactor Facility (Building 21) and the Hot Cell Facility (Building 23). However, the values were below the release criteria (25 R/hr; 15 R/hr background plus 10 uR/hr). l 13

1 Building 27 Final Radiological Survey Report -> mm momers The results of the five (5) soil samples collected during the confirmatory survey showed trace concentrations of Cs-137 (near background levels) and no detectable Co-60 or other gamma emitters other than naturally occurring radionuclides. The soil sample results are provided in Table 8. The results and the locations of the other confirmatory surveys are provided in Table 7. 1 Conclusion Final contamination and radiation surveys as well as soil sample results provided in this report for l Building 27, demonstrate that the building and surrounding " footprint" area (the sidewalk surrounding the building) meet the approved guidelines for release to unrestricted use, i i I r 14 4 l

i i Table 1: USNRC'S ACCEPTABLE SURFACE CONTAMINATION LEVELS ' Nuclides Average Maximum

RemovableW l

W (dpm/100cm ) (dpm/100 cm') (dpm/100cm ) 2 8 U-nat, 235U, 23 U, & associated decay products 5,000 a 15,000 a 1.000 a Transuranics,226Ra, 22 Ra, 23g, 22 Th, 23'Pa, 100 300 20 227Ac,125g,129; Th-nat, 232Th, "Sr, 22'Ra, 224Ra, 232U,126;,i3'I, 1,000 3,000 200 isig Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except "Sr and other noted above. Where surface contamination by both alpha-and beta / gamma-emitting nuclides exists, the limits a established for alpha-and beta / gamma-emitting nuclides should apply independently. b As used in this table dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, an geometric factors associated with the instrumentation. Measurements of average contaminant should not be averaged over more than I square meter. c For objects ofless surface area, the average should be derived for each such object. d The maximum contamination level applies to an area of not more than 100 cm, 2 2 e The amount of removable radioactive 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 ofless surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped. f The average and maximum radiation levels associated with surface contamination resulting from 2 2 beta-gamma emitters should not exceed 0.2 mrad /hr at 1 cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber. 15 i l i

i l Table 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS 8 I Nuclides* Average *d Masimum # Removable *d 6 8 8 2 (dpm/IO0cm ) (dpm/100cm ) (dpm/100cm ) U-nat,2"U,2"U, & associated decay 5,000 15,000 1,000 products Transuranics,22.Ra,22 Ra, 2'*Ih, 22 Th, 100 300 20 2"Pa, 22'Ac, '25g, 2,g u Th-nat, 232Th, "Sr,22'Ra,22 Ra,222U, i21, 1,000 3,000 200 mg,ing Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except "Sr and other I noted above Where surface contamination by both alpha-and beta / gamma-emitting nuclides exists, the limits a established for alpha-and beta / gamma-emitting nuclides should apply independently. b As used in this table dpm (disintegrations per minute) means the rate of emission by radioactive I material as determined by entrecting the counts per minute observed by an appropriate detector for background, efficiency, an geometric factors associated with the instrumentation. Measurements of average contaminant should not be averaged over more than I square meter. For c objects ofless surface area, the average should be derived for each such object. d The maximum contamination level applies to an area of not more than 100 cm. 2 I The amount of removable radioactive material per 100 cm of surface area should be determined by e 2 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 efliciency. When removable contamination on objects ofless surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped. f The average and maximum radiation levels associated with surface contamination resulting from beta-I gamma emitters should not exceed 0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm, respectively, 2 2 measured through not more than 7 milligrams per square centimeter of total absorber. Guidelines For Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses For byproduct, Source, or Special Nuclear Material, also known as "Decon-1" incorporated into GA's State of CA Radioactive Materials License. 16

Table 3: List ofInstruments Meter Detector Detector Calibration Efficiency Range .Backgreemd Description -S/N ~S/N Dee Date (epm) (cpan) Ludlum Rate Ludlum S/N 086238 07-08-98 20.00 % Four Linear See Table 4 The instmment is a gas-flow proportional counter with Meter Model S/N 086238 08-27-98 20.00 % Ranges 0-an active probe area of434 cm. The detector and rate 2 Model 2221 43-37 S/N 086238 09-16-98 21.83 % 500,000 & meter are combined and mounted on a roll around S/N 97287 434 cm2 S/N 083265 11-19-98 l 21.69 % One Log 50-cart. The instrument features a static-flow system, Alpha S/N 083265 I l-24-98 21.69 % 500,000 quick connects, a portable gas bottle and a means to S/N 086238 11-27-98 21.90 % adjust the height of the detector from the floor for S/N 086238 01-19-99 21.40% optimum performance. Ludlum Rate Ludlum S/N 083293 06-04-98 21.14 % Four Linear See Table 4 The instmment is a gas-flow proportional counter with Meter Model S/N 094120 10-29-98 21.85 % Ranges 0-an active probe area of 434 cm. The detector and rate 2 Model 2221 43-37 S/N 086213 01-07-99 22.04 % 500,000 & meter are combined and mounted on a roll around S/N 84459 434 cm2 One Log 50-cart. The instrument features a static-flow system, Beta 500,000 quick connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance. Ludlum Rate Ludlum S/N 083265 01-06-98 20.30% Four Linear See Table 4 The instrument is a gas-flow proportional counter with Meter Model S/N 083265 07-08-98 21.85 % Ranges 0-an active probe area of 434 cm. The detector and rate 2 Model 2221 43-37 S/N 094119 11-03-98 21.85 % 500,000 & meter are combined and mounted on a roll around S/N 73701 434 cm2 S/N 094119 12-17-98 21.85 % One Log 50-cart. The instrument features a static-flow system, Beta S/N 093600 12-30-98 24.13 % 500,000 quick connects, a portable gas bottle and a means to S/N 093600 02-17-99 23.26 % adjust the height of the detector from the floor for optimum performance. Ludlum Rate Ludium S/N 119444 04-27-98 31.68% Four Linear See Table 4 The instmment is a gas-flow proportional counter with Meter Model S/N 119444 07-20-98 35.SN & Ranges 0-an active probe area of 100 cm. I 2 Model 2221 43-68 S/N il9444 08-12-98 35.50 % 500,000 & S/N 84423 100 cm2 S/N I19444 I I-05-98 27.37% One Log 50-Beta S/N 119444 03-11-99 27.25 % 500,000 17 I

Table 3: List ofInstramients : Meter De*c-tv Detectcr ' Calibration' - EfHelency Range. Backgresad ~ r- - " " . S/N S/N ~ Lbe Date (epsm) .(cpen). Ludlum Rate. Ludlum S/N 120477 04-27-98 31.68 % Four Linear See Table 4 The instrument is a gas-flow proportional counter with Meter. Model S/N 120477 10-20-98 31.68 % Ranges 0-an active probe area of 100 cm,. 2 Model2221 43-68 S/N 142540 11-03-98 26.76 % 500,000 & - S/N 86332 - 100 cm2 S/N 142540 01-14-99 28.80 % One Log 50-Beta S/N 142540 01-22-99 28.95 % 500,000 03-02-99 29.80 % Ludlum Rate Ludlum S/N 120477 11-03-98 27.06 % Four Linear - See Table 4 The instrument is a gas-flow proportional counter with Meter Made! Ranges 0-an active probe area of 100 cm. 2 Model2221 43-68 500,000 & S/N 148436 - 100 cm2 One Log 50-Beta 500,000 Ludlum Ludium S/N 145%7 04-15-98 23.34 % Four Ranges concrete so.140 The instnament is used for beta / gamma surveying. The Model3 Model S/N 145%7 07-13-98 23.34 % 0-100,000 detector has an active probe area of 15 cm. ~l 2 g,,c,,,,,,,,, S/N 143349 '44-9 S/N 145%7 10-21-98 23.24 % gno 15 cm2 Beta, Gamma Metal 40100 - Ludlum ? udium S/N 145%3 04-15-98 23.24 % Four Ranges concrete so.140 The instrument is used for beta / gamma surveying. The Model3 Model S/N 145%3 10-08-98 22.05 % 0-100,000 detector has an active probe area of 15 cm. 2 g,,c,,,,,,,c, S/N 138880 44-9 S/N 145%3 I l-02-98 22.05 % gno 15 cm2 S/N 145%3 12-28-98 22.05 % Beta / Gamma Metal 40100 Ltidium Lud:um S/N 145701 05-12-98 21.58 % Four Ranges 0 Alpha scintillator ZnS(Ag) with an active probe area - Model 12 M del S/N 145701 10-15-98 21.58% 0-500,000 of 50 cm. 2 43-65 S/N 145701 Il-03-98 21.58 % S/N-50 cm2 S/N 145701 11-19-98 21.58 % 138747 Alpha 18 J

s Table 3: List ofInstruments Meter Detector Detector Calibration Efficiency Range

Background

Description S/N S/N Due Date (cpm) (cpm) g Ludlum Ludlum S/N 142349 04-27-98 21.58% Four Ranges O Alpha scintillator ZnS(Ag) with an active probe area Model 12 Model S/N 142349 10-05-98 21.58% 0-500,000 of 50 cm. 2 S/N 138738 43-65 S/N 142349 10-15-98 21.58% 2 50 cm Alpha Ludlum Ludlum S/N 076230 09-02-98 21.22 % Four Ranges 0 Alpha scintillator ZnS(Ag) with an active probe area Model 12 Model 0-500,000 of 50 cm. 2 S/N 73920 43-65 50 cm2 Alpha Ludlum RCA 6199 N/A 03-03-98 N/A Five Ranges 10-18 Used for measuring extemal dose rates on the surface Model 19 coupled to a 04-03-98 0-5 m R/hr R/hr and at one (1) meter from the surface (i.e., initial Micro-R Nai(TI) 06-05-98 ground floor surveys). The scintillator [l" x I" Nat Meter Scintillator 08-26-98 (TI)] is mounted intemally. S/N 144068 11-03-98 Ludlum RCA 6199 N/A 05-08-98 N/A Five Ranges 10-18 Used for measuring external dose rates on the surface Model 19 coupled to a 08-05-98 0-5 mR/hr pR/hr and at one (1) meter from the surface (i.e., initial Micro-R Nal(TI) I l-03-98 ground floor surveys). The scintillator [1" x 1" Nal Meter Scintillator (TI)]is mounted intemally. S/N 144746 Canberra Gas Flow N/A As needed 30 % N/A Varies with Canberra Model 2400 Low Level a/p gas proportional Low Level Proportional Sample counting system used to count wipes for removable a/p Counter Detector contamination. Results are usually reported as 2 dpm/100 cm. I i 19

i .I l1{l)i Ilil! Il!1 i i ll l l IlllI ill l l hig h a gn isu me n t o sy it s p A r. irc Co t s Mec eD yte pd ocm s u ui tr n c a pm e r S e aG my mi t r a u Gp d h n t o )m iwl u e p r s gp e m k (c iar c aS s a t V n B e mur e) gm A ts n / n ap I R (e N fo ts iL y h 02 t c ie n wl e p 3 em i s c e m i a raS lb E V aT noe d i t e t a d arD ee b e n i l u s aD C A ro tcN A e/ / S N teD ym r t r u o iri o t u nt c P a ec e h mt t e e grD D e i f G I yp a aom r r mc r eN e s e te/ b mrots S M nat y c ages C p S l

4 J Table 4: Background Measurements (Obtained from Building 13) Ludlum Model 2221 Rate Meter s/n 84423 with Model 43-68 Probe s/n 119444 2 100 cm Beta detector (Efficiency = 35.50%) Background Material Average of10 Measurements 1 MDA minute each (epm

2 o)

(dpm/100cm ) 2 Concrete 502

40 301 Concrete Block 412
52 274 Metal 364
32 258 Drywall 272
22 224 Background Material Average of10 Measurements 2 MDA 2

minutes each (cp2m

2 c).

(dpm/100cm ) Concrete 1011

48 212 Concrete Block 803
64 189 Metal 655
70 171 Glass 503
64 151 Ludium Model 2221 Rate Meter s/n 86332 with Model 43-68 Probe s/n 142540 2

100 cm Beta detector (Efficiency = 28.80%). Background Material Average of10 Measurements at MDA 2 1 minute each (cpm

2 o)

. (dpm/100cm ) Concrete 531

56 381 Concrete Block 447
56 351 Metal 281
44 280 Drywall 287
44 283 Background Material Average of 10 Measurements 2 MDA 2

minutes each (cp2m

2 o)

(dpm/100cm ) Concrete 1059

74 267 Concrete Block 919
108 249 Metal 550 A 52 194 Drywall 581
38 199 Glass 608*42 204 21

Table 4: Background Measurements (Obtained from Building 13) Ludlum Model 2221 Rate Meter s/n 148436 with Model 43-68 Probe s/n 120477 2 100 cm Beta detector Background Material Average of10 Measurements MDA 1 minute each (cpm

2 c)

(dpm/100cm ) 2 (Elliciency = 25.04%) Concrete 554*56 448 Concrete Block 437 36 399 Drywall 273

40 318 Background Material Average of 10 Measurements MDA 2 minutes each (cp2m
2 c)

(dpm/100cm') (EITicleacy = 27.06%) Concrete 933

38 268 Concrete Block 802
28 249 Metal 575
28 213 Drywall 510 30 199 Ml Ludlum Model 2221 Rate Meter s/n 73701 with Model 43-37 Probe s/n 083265 Beta Floor Monitor Background Scan Results: 434 cm detector (Efficiency = 21.85%)

2 Background Surface Material Beta / gamma Scan Range (epm) Concrete 1795-2030 Concrete Block 1281-1554 Metal 1151-1425 Drvwall 906-1050 22

l Table 4: Background Measurements (Obtained from Building 13) Ludlum Model 2221 Rate Meter s/n 84459 with Model 43-37 Probe s/n 083293 Beta Floor Monitor Background Scan Results: 434 cm (.etector (ElTiciency = 21.14%) 2 Background Surface Material Beta / gamma Scan Range (cpm) Concrete 1400-1570 Concrete Block 1174-1409 Drywall 770-937 Metal 816-1047 Ludlum Model 2221 Rate Meter s/n 97287 with Model 43-37 Probe s/n 086238 Alpha Floor Monitor Background Scan Results: 434 cm detector (Efficiency = 20.00%) 2 Background Surface Material Beta / gamma Scan Range (cpm) Concrete 0-20 Concrete Block 0-20 Drywall 0-15 Metal 0-20 23

Table 5: Results of Final Surveys in Building 27 Figure Type of /

of Fixed Musimum Scan Results Scan Results.

. # of Maximum Notes and/or Exposure Rate 8 Measurement Measurements Result 434 cm a 434cm p Smears . Result Sample Results1 Reage - 2 2 2 2 and/or. (with 100 cm (dpm/100 cm ) (epm range) (cpm rnage) - (dpm/100 (concrete /peint - (pR/hr) ~ Location detector) em ) chips) 2 Affected Area of Building 27 Concrete /hietal 100% a 100%p 5 Floor Scans 7-41 800-3500 Concrete /htetal 113 599 De concrete floor was aggressively decontaminated using the blastrac unit (twice). After this the floor was Floor scanned using the 434 cm floor monitors (final survey); results (shown above) were as high as 3500 cpm 2 Fixed (higher than normal background readings). Because of this,113 of the i m grids (which had the highest floor hicasurements monitor readings) were surveyed using the 100 cm detector. He maximum activity detected ii any of these 2 2 grids was 599 dpm/100 cm, below the release criteria. Concrete /htetal 44 482 Rese fixed measurements were taken in accordance with the final survey plan on a grid system. 8 Floor hicasurements were taken every 4 meters using a 100 cm beta gas flow proportional detector and ratemeter. 2 Fixed 2 minute measurements 6 Lower Wall 100% a 100% p Scans West Wall 0-84 675-1850 l Below 2 m North Wall 0-29 775-1490 South Wall U-34 660-1800 East Wall 0-24 715-1960 6 Upper Wall West Wall-25% a and p 0-21 875 - 1700 Scans North Wall-10% a and p 0-6 860 - 1050 Above 2 m South Wall-10% a and p 2 - 15 800 - 1150 2 (434 cm ) East Wall-10% a and p 0 - 13 840 - 1375 Walls 24 467 8 Fixed 2 minute i measurements 24

~ Table 5: Results of Final Surveys in Building 27 Figsre Type of

of Fixed.

Maximum Scan Results Scan Results

of -

Maximum Notes and/or Exposure Rate - 8 Measurement Measurements Result '434 cm a 434 cm p Smears Result Sample Results Range 2 2 2 2 and/or (with 100 cm (dpm/100 cm ) (cpm range) ' (cpm range) (dpm/100 ( cacrete/ paint ( R!br) Location detector) 2 cm ) chips) 12 Overhead 25 479 33 77 a A/C& heating (2 minutes 21 p ductwork each) (external fixed l measurements and smears) 12 Overhead 7 < 10 a A/C& heating < 10 p ductwork (intemal smears) 13 Fire Sprinkler 30 17 a system 41 p 14 I-beams and 15 < 171 24 90 a lights (2 minutes 24 p each) 8 Smears 68 < 10 a (Floors and y4 p Walls) 10 Fixed 12 < 196 1I readings were on measurements

4. east wall painted walls and one before paint

4. west wall on a painted window sample removal 2-north wall 2-south wall 25

Table 5: Results of Final Surveys in Building 27 Figure Type of . # of Flued Maximum Scan Results Scan Results

of Maximum Notes and/or Exposure Rate 2

2 Measurement Measurements Result 434 cm a 434 cm p ' Smears Result Sample Results . Range 2 2 and/or (with 100 cm (dpm/100 cm ) (cpm range) - (cpm range) (dpan/100 (concrete / paint. ( R/hr) Location . detector) cm*) chips) 10 Fixed 12 290 1I readings were on measurements 4-east wall painted walls and one after paint

4. west wall on a painted window sample removal 2-north wall 2-south wall 10 Paint Sample 12

<10 a a/p results 251 $ 10 Exposure Rate 15-19 Measurements (57 readings) 17 & Concrete Lined 33 529 0 49 400-600 34 <10 a Final survey done 15-28 I8 Trench (with 100 cm <10 p aRer removal of utility 2 detector) lines and soil / debris Trench formed 420-970 22-26 2 after removal of (with 100 cm " hot" drain line detector) 26

Table 5: - Results of Final Surveys in Building 27 Figure ' Type of ' # of Fixed _ Maximum Scan Results Sena Results

of

~ Maxinessa Notes and/or ' Exposure Rate 2 2 Measurement Measurements Result 434 cm e . 434 cm p Smears Result Sample Results Range 2 2 and/or (with 100 cm (dpm/100 cm ) '(cpm range) (cpm range) (dpm/100 (concrete / paint ( R/hr) - 2 1mation. detector) em ) chips) Unaffected Areas 5 Concrete South 4 - 64 South 1600-2650 Sidewalk Scans North 7 - 54 North 1400-1900 East 4 - 84 East 1650-2900 West 5-71 West 1200-2500 2 Concrete 10 977 These fixed measurements were taken with the 100 cm detector in the grids having the highest readings 2 Sidewalk fixed obtained with the 434 cm floor monitor (results above) because the readings we e higher than normal measurements background readings. II Concrete (26) 9 < 10 a 14 - 21 South - 4 521 sidewalk (fixed top North - 4 463 measurements, gast - 9 771 smears and "*58 - 9 729 exposure rate) 5 Scans of Unafrected 6-18 1250 - 2200 14 -16 Floor Areas inside Building 7 Scans of UnafTected 6-9 1050 - 2200 Wall Areasinside Building 9 Fixed (18) (14) measurements & 8 on floor 484 5-floors < 10 a smears in the 10 on walls 771 9-malls < 10 p unafrected floors and walls 9 Overhead structures 12 < 10 m (ductwork, I-beams < 10 $ and lights)in Unaffected Areas 27

Table 6: Results of Final Soil Sameples CoIIected in Buildian 27 - 1 RedlenacNde Concanenaien (pChir)' Sainple ID '.2'*U ' 2"U - 2'*Th - ' 2 Ra TotalThorises ' 8"Cs "To- ~ Average of (22'Th) . 2'*Th +.2"Th 661.6 kev peak-t173/1332 kev peak - Average of. 92.77 kev peak 186 (144) kev peak 583/238 kev peaks - - Average of. staana k,v - h. SI 1.80

0.77 0.10
0.08 0.77
0.11-

-1.56

0.26 233 ND-ND SI-A 1.70
0.83 0.21
0.11 0.82 0.13 1.57 0.28 239 ND

ND S2 1.49

0.16 0.07
0.08 0.69 0.I6 1.24
0.43 1.93 ND ND S3 1.41
0.61 0.08
0.08 0.81
0.11 1.45
0.46 226 ND ND L

S4 1.72

0.73 0.17
0.09 0.66
0.16 1.20 038 1.86 ND ND S5 1.19
0.70 0.10 0.09 0.67
0.11 1.15 035 1.82 ND ND S6 1.24
0.77 0.15
0.10 0.72
0.18 1.50*034 2.22 ND ND S6-A 1.61
0.52 0.16
0.05 0.67
0.09 1.12 0.29 1.79 ND ND S7 1.05
0.43 0.13
0;:

0.52 i 0.08 0.88

0.24.

1.40 ND-ND-S8 1.00

0.47 0.08 i 0.05 1.44 i 0.21 0.91
0.25 235 ND ND S9 1.56
039 0.13
0.06 0.57 + 0.09 0.87 0.25 1.44 ND ND SII 2.02
0.27 (0.11
0.1I) 0.95 0.05 1.4 0 0.16 2.35 ND ND

[ S11-A 2.35

0.90 0.18 0.09 1.10
0.25 1.72 0.46 2.82 ND ND l

S12 2.7i

0.90 0.17 0.11 1.19
0.15 2.48
0.52 3.67 ND ND r

28

Table 6: Results of Final Soil Samples Collected in Building 27 Radionuclide Concentration (pCVs) ' Sample ID "U "U "Th

Ra Total Thorium "Cs "Co Average of

("Th) Average of 92.77 kev peak 186 (144) kev peak 583/238 kev peaks Average of "Th + "Th 661.6 kev peak 1173/1332 kev peaks itman a hv -a S13 1.68

0.74 0.27 i 0.10 0.98 i 0.13 1.64
0.48 2.62 ND ND S14 2.05
0.83 0.18 0.09 0.98 0.12 1.56
0.41 2.54 0.15
0.06 ND S15 2.05
0.70 0.19 i 0.10 0.95
0.13 1.66
0.45 2.61 ND ND SIS-A 2.18 0.53 0.15
0.07 0.99
0.11 1.42i 034 2.4 i ND ND S16 2.0210.61 0.16
0.07 239*030 136*031 3.75 ND ND S17 1.68
0.45 0.16
0.06 0.77
0.09 1.23
0.26 2.00 ND 0.06
0.06 S18 1.39 0.57 0.11
0.05 0.61
0.13 1.06 0.26 1.67 ND ND S19 1.17
0.69 0.09
0.08 0.69 i 0.12 135*0.28 2.04 ND ND SI9-A I.36 + 0.46 0.13
0.05 0.67 0.08 1.12
0.26 1.79 0.80
0.07 ND S20 1.66 0.65 0.08
0.05 0.53 0.16 0.76
0.26 1.29 ND ND S21 0.76
0.55 0.09 0.06 0.50
0.08 0.87
0.23 137 ND ND S22 1.56
0.59 0.15* 0.06 0.65 i 0.09 0.86
0.28 1.51 ND ND S23 1.42
0.58 0.08
0.07 0.58
0.11 I34 *039 1.92 ND ND S24 1.33
0.54 0.13 0.07 0.71
0.11 0.99 0.29 1.70 ND ND 29

Table 6: Results of' Final Soil Samples Collected in Building 27 Radionuclide Concentration (pCVg) ' Sample ID "U "U 22*Th " Ra Total Thorium "Cs "Co Average of . (8'2Th) Average of 92.77 kev peak 186 (144) kev peak 583/238 kev peaks Average of 2 *Th + 232Th 661.6 kev peak 1173/1332 kev peak nami n k,v k. S25 1.63

0.51 0.13 i 0.06 0.62
0.10 1.07
0.29 1.69 ND ND S26 1.06 i 0.5 I (0.25 0.26) 0.54
0.09 0.88*033 1.42 ND ND S27 1.08 0.41 0.05
0.05 0.57 0.09 0.89i035 1.46 ND ND S28 1.26
0.49 0.1 I.06 0.55
0.08 0.95
0.25 1.50 ND ND S29 1.08
0.51 0.12
0.05 0.54 0.15 1.12
0.58 1.66 ND ND S30 0.90 0.54 0.08
0.09 0.57 0.14 1.I8*039 1.75 ND ND S31 1.22
0.46 0.07
0.05 0.54 0.07 0.83
0.28 1.37 ND ND S32 0.67 + 037 0.07 0.04 1.01
0.17 0.66
0.17 1.67 ND ND S33 0.86 039 0.04 0.05 0.28
0.05 0.42
0.I9 0.70 ND ND S34 0.77 030 0.06
0.03 0.25 + 0.05 0.42
0.16 0.67 ND ND S35 0.49 0.40 0.06 0.04 0.25 0.06 0.49 0.17 0.74 ND ND S36 1.01 i O39 0.10 0.05 031 t 0.05 0.52
0.17 0.83 ND ND S37 0.69
0.41 0.06
0.04 034 0.05 0.51
0.19 0.85 ND ND S38 0.84
037 0.05 + 0.04 03 I i 0.06 0.49
0.17 0.80 ND ND 30

Table 6: Results of Final Soil Samples Collected in Buildina 27 - Radiewscude Carcentrenon (pCVz) ' Saimple ID "U "U "Th - " Ra Total Thoriumi Cs "Co Average of. . ("Th) 92.77 keVpeak 186 (144) kev peak 583/238 kev peaks . Average of ? "Th + "Tb.. . Average of - 661.6 kev peak - 1173/1332 kev peaki tsami n k,v o,.h. S39 0.64 *035 0.06

0.04 031 i 0.05 0.60* 031 0.9I ND ND S40 0.90 + 0.41 0.07
0.04 035
0.06 0.55 0.40 0.90 ND ND S41 1.09
0.45 0.09
0.04 030* 0.06 0.59
0.19 0.89 ND ND S42 0.69
0.40 0.10
0.04 0.22 0.06 0.46
0.15 0.68 0.03
0.04 0.10* 0.06 S43 0.64
034 0.05
0.04 0.27 0.05 0.45
0.16 0.72 0.02
0.02 ND Background concentrations act subtracted from the results. The results are all
20. Samples counted for 30 minutes except S-1I which was counted for 2 i

hours. ND= < 0.1 Cs.137 < 0.1 Co-60 31

r, w m use, - Table 7: Internal GA Confirmatory Surveys for Building 27 Maximum p Fixed Scan Results

of Maximum Results '
of Soil Exposure Rate Range Measurements 434 em p Smears (dpm/100 cm ) '

Samples (pR/hr) 2 2 Location (with 100 cm detector) (cpm range) 2 2 (dpm/100 cm ) Alpha Beta Suspect Affected Area-Floor 482 1317-1867 35' < 10 17 12 - 19 Suspect Affected Area-Walls 417 962-2022 Suspect AITected Area (Trenches & 939 5 2 Concrete Excavations) Unaffected Area Floors 380 1611-1852 (Office / Mechanical) 14 - 15 Unafrected Area Sidewalk 968 1414-2194 12 - 21 (Around Building) ' includes walls, floor,1-beams, overhead ducting, sprinkler system, and other overhead structures. 2 See Table 8 for results of soil samples. I i 32

Table 8: Results of Soil Sample Results Collected in Building 27 during Internal GA Confirmatory Survey Raummende Concentranen (pCVs) '

Sample ID

' '"Cs "Ce - 2*Th~

Ra.

Total Thonum "U- . "U -- Average of 1173 med Average of ("Th) 661.6 kev peak' - 1332 peaks - 583/238 kev peaks Average of 8"Th + "Th 92.77 kev peak 186(144) kev poet 338/911 kev peaks - 27S-98-001 ND ND 0.97 0.07 1.94 0.29 2.91 1.70

0.41 0.18
0.05 27S-98-002 0.06
0.04 ND 1.00 0.07 1.64
0.25 2.64 1.91
0.37

-0.16

0.01 27S-98-003 0.02 t 0.01 ND 0.41 0.02 0.83
0.07 1.24 0.79
0.I2 0.06
0.02 27S-95-004 0.03 0.02 ND 0.59 0.05 1.02
0.15 1.61 1.56
0.35 0.12
0.03 27S-98-005 ND ND 0.26
0.01 0.45
0.03 0.71 0.51
0.04 (0.02 i 0.01) 3 Background concentrations p.sl subtracted from the results. The results are all
2o.

Laboratory Countine Times 27-98-001 1 hour & 12 min. 27-98-002 I hour & 30 min. 27-98-003 10 hours & 30 min. 27-98-004 I hour & 30 min. 27-95-005 10 hours & 30 min. ND= < 0.1 Cs-137 < 0.1 Co 60 33

1 Table 9: Background Soil Sample Results ' Sample Cs-137 Th-228 Ra-228 Total U-238 U-235 1 ID 8 (Th-232) Thorium Th-228 + Th-232 Radionuclide Concentrations (pCi/g) AJ ND 1.28

0.07 1.47 0.14 2.75 1.98
0.31 0.15 0.03 G2 0.12 0.03 0.92
0.07 1.01
0.12 1.93 1.86 0.29 0.12
0.02 AC ND 1.29 0.07 1.34
0.14 2.63 2.27 0.27 0.20 0.03 BKG-1 ND 1.40
0.16 1.44
0.28 2.84 2.06 0.48 0.19
0.06 BKG-2 ND 1.54
0.15 1.57
0.27 3.11 2.30 0.45 0.17
0.05 BKO-3 ND 1.40
0.I4 1.62
0.26 3.02 ND 0.I9
0.05 BKG-4 ND 0.67
0.09 0.84
0.17 1.51 1.15
0.37 0.09
0.04 BKG-5 ND 1.51 0.16 1.79
0.31 3.30 2.77 0.67 0.12
0.06 BKG-6 ND 0.68 0.09 0.76
0.I6 1.44 ND 0.08
0.03 BKG-7 ND 1.17 0.12 1.28
0.22 2.45 1.33 0.43 0.11
0.04 Mean
2 o I.I9 0.64 1.31
0.68 2.5
1.32 2.03 0.93 0.14
0.09 Samples gamma scanned for I hour.

ND= < 0.1 pCi/g for Cs-137, < l.0 pCi/g for U-238 2 Samples collected in June and August 1993, typically about 1-2 miles from the Building 37 site at the following locations: AJ Collected on a hillside west of Building 39 & northwest of building 37, ~3' from GA's fence. j G2 Collected about 1200 feet west of Bldg I (near T.P. RD.), and ~7/8 of a mile southwest of Building 37. l AC Collected about I mile southeast of the main site & about 2 miles southeast of Building 37. BKG-1 Collected about I mile from Building 37 at the Scripps Hospital Entrance, east of Genesee Ave. l BKG-2 Collected about 1.2 miles from Building 37 at Sorrento Court Rd. by North entrance to Post Office. ] BKG-3 Collected about 1.5 miles from Building 37 at Sorrento Vista Parkway near Lusk Blvd. South. j BKG-4 Collected about I mile west from Building 37, west off Genesee corner of North Torrey Pines Road and Torrey Pines Scenic Drive f BKG-5 Collected about 2 miles west of GA off of La Jolla Shores Drive. BKG-6 Collected about 2 miles northwest of Building 37 on North Torrey Pines Road l BKG-7 Collected about 2 miles near V.A. Ilospital on La Jolla Village Drive (southwest) i l 34 i

4 b ll3::'n

C:::l$$2:

l::::::r wr2 3.M., W 7 end Iam E e N

numa aume.e neuenea inna r s a seus., .i N Nv.m aima. h l JNDU M N {

l::1,

l::::

i i M\\i s

=::. c=

15 L ', "g Gip f N $Dammm.s ST-

=:= rm-llll::'.".e.".",

[ NI DNSs J

1, llll:::::ll::::lllll:,-

w r.n a / {- llll:::= :::l::::::l::"", 51 ~$sw m.nene Qhbi OPENSPACE r llll:::.'::lll*=e - 6p ,{ CONTROLLED L a.uene a se v ,emme., e d's' s' & N' Wsw*'"r.*."m*,, [ llll:::: m ACCSS "".l.':'."" r,,/' 4;' / N: /

=::

s ~. ,',e a a uenee anos.nu a r 1 yypgg \\j ~ % 21 f N [##

1 a

g Y gg-a-2 LOTS k 8 g co"ur 4: s$ 0 2 y g i f I i M 10 4 L =~> 1. / t' ~ (

ENe %%cp=

LOTS sg, Y UCSD f --- RNONG PROPERTY UNE I e no son no 1o00 y i:;p 77/m i Figure 1: Plan View of General Atomics Site L I

&g NN3g \\! y // ~ s Y s O g

\\

s au j '- n n,,,, ./ / },, " g O _._____) g t V q 3 3 >+,, v a" ^ b O\\ \\ 9 s /," \\ 9 (/ / t. A ~ I l.'. Q N e \\ 7 ,A

Il!Ill! 1 1 ln 4 5 6 1 1 1 2 1 1 1 3 h_ U 2 d U 2 3 1 1 1 1 i 2 h V s 0 1 1 1 n 1 1 o i ta 2 c i f i h V d 8 9 o 0 0 M 1 1 o t g ro i h V r P 6 7 0 0 1 1 7 2 g g n i d , 0 Y l i e H ^ N1k L u B ( A B ~ ~ 2 5 5 g 0 0 0 m h V1 3 1 1 er Q ug i r [ ( F Z 0 0 0i 3 4 1 0 0 1 1 1 1 t O Z H 1 0 T 0 0 R 1 1 ON ) y Z L

W S N-Figure 4: Building 27 (EA-1) Buik2 ng View of Affected End Unaffected Area (Current Status) ' .1__. .i, ; e t 2 i :. :. t !5 l 6 l7 ' e . m_._4p: g_213 i 4 i ' 1 1 7 + q __l 4. p.,' a ; to ; 11:12 (13114 ;ts :16117i18 ~ 19 [20 ) 21 i 22i 23! 24 l 25126 :27 '28 :29 30 l31 132 33134.35 36 '37138!39 40 f 1 i 1 p y._ p-4 q q.q _;.....g.~ _ ; _4 - _u-_ L g4 y._.w.+_.+ -.p_p t -, -_ _.._4-2. 4.,t_ ..~.;_. p _';.._ _i..A M: ; i j i i i r i t. t

- ; e 1

i i i _ I-. 4... 3 m p _p.4_.hb 4 a 4-2I ~ J4 __ #. s 4_4 .J

L p

M q. -

u. 4.t _.ma;. u u.'w! _ -.

a._._,. _. +. a._ A i ! a 1-p! i i i i a._ L.. !_4. s i _t tw i._! _a_ #& i ! ; i I .. _! i.i lt u_L.: 'I i t i i w.1_l i i ~l-B ! ! I : ! ! i

4. _ i...% x.L.a y p _.,l.~,.__p.n L_i_l,_4_L',A +_2_ e.L.n % _._

) 1 ! : i i a __ g-4.w; i ~ ! i : ' i ~ i . i 'i ' t i 4 _w.. A .__ v._. 4, _ _.. g _; C ; i i > - r f i + ' s - i t-1 ; 1 t t i ;.i i i i ; i t i i i i -gm_ g __f 4_ ___ -4 _ p 4 % _. .I __ ; 9 7._ p p g .m ._ 7.. gp.q .I; p I 7.__.7

p g 7- _y_

g y _.m_~ z _9 4 .p_ h e O I i I l l I 1 l 5 1 i l I I l-i '*^ \\ ' }_ _-'[7 4_ 7_ p __p 4_ 3iSIDEWALKUNAFFECTED ARE.A.l_.4 's ,i.. ;' _. p.,. _ _ _ ~. - + r.4__ q._7_- l ,! l, F i; ,1 ! ' ' 9.q --i t

3

_..-__t l l i _ i ' E ! ! ' ! i i ' i. I i i . b.. _- w 7 I h .___.u.-_..=,.M'_4_.,'t---'--'H- +. ...,t u _.s_.n_ M_14_ 4._u .s _u.. L._..- +._x -4_ -.a__+.,-. +. n._ n 4+_ G L i: s,m._q _p. ..--- l'

i

! - 1'

i ; i ! ': i i

4' i - i t-i - + 3 r _._, i i 4 ~ ! i : r i r - = c -- < f M - -Y -- b ' '- --+-- - P-- 4 ' E ----M -- P - J '-- +t --+ f- ' - - f ' ' -b --[ -+ L

i

~~ * * ' ' '- 'Q

. _ _..... i _ ! _.p _.c i I M-4" .l H : ? ! t ,. i i w_.i a. ( i ; i ! _.4.._ t __4, +_ p

a. _ p i.

_ a

.m

-q._. i, _4 _4 -.J.-- _4._. 2... r. .a - g +._ r _ -r l' ' I * ' i l I i i ! ! j A#ected Ares! ! i i su mu 4.- c t._L_a_: - ;- a m.. e,l_. n._( +. u w a ! i ' i i i I i ! .1 i + __ a m 1 u_7 m La _m.._ J i l' _[. ' _. '.. l i ~ i i ! l ! __q. '..._ g - 1 _i. ' _.. { ' i i i i i i .l _a 1 ._. { . _u wu + +. + L ^ t i i ,. 4. _ 1 _.p. L---- . p 4 _i4 +. _ L _4 __4-J. A 1-. ..t._4 _ n.1_?W. -.j _._ __L.4 _ _.. p. 2 J. a._ u.4], t u..., - . _ a _ 4. _" _! ! ~ , 1' ' r 1 i ; i ' I: ' ! { j 1 - l-y i j t' i = + r.L __. 1 _t. m_ t I, i t_._ i +' i I ' g w', 1a._.. 1m r a i, ! N. r 2 ( t e Q_4 2 1 i O ~ 3 - 1. _ 4._. _ r _ _ i - - ..4. -4~_ i - +.~. g_. u A.n y.- p.g _ +-- b... &, g!.py- _ j._ e ~.-u l uriancrod A,,, i. I t

r

} i i i j i ; - i : ; i i>.!. 4 , l I,.,.+ i ._,j-t 4 y.-- r.. e .f. 4._.. i ! -.H 1wi-r p.- _m-t i r r p + _. _ - p m -..q ! i 1 i i + ' ~ _. _. g.. _ .a _._p_ _L .:._.._.1 J - p' !_ y P I a.a. e.1 +. _! _a; _ w1 = w+ +%+ et_ t 1'l a % t I i. s - + - Q ' i l [ ' ! i, I l i ~ i i f i

'l 1 _-

i ! e. [4 . - + s-- R i 1 !_ _: !._ i M!._j j i i .. r _.t_:-j i i.smiwM.x.d.NAFEC.TEd AM A. 4_ i' ]._.f__.!~I --._l-4_a Q,j j i l y_j+zi _L 3__{,j__L M,,__ L j,j__j__u i,[_[_J j+,1 M,[ f 2 _2,__1.i.l_,( 7 {j - I "l k _e g ~ s L, .L._ T 1 4 .$+ b U

.i i _. 4 A----.m..i

.-4 u__ .-.~._-c..- 4 -4.-o.-+-- j_-..s-4 . m 1. 2 _ .L. 4 - ' .} ..._n._. _s ,._.4._l... i ' x-et--.- 7.. ! ~ ~ ! i-l l,.

j s

-.A_%- .,i ! .! _ 1 i ! ' ! l 4 4 4 4 - i 4 y .x r, t. 1' t y j t, i r i i Ii - i i 4 _,_ t _. f -... +i.., -.m - 4 1 1 2. 4 .u 4 i i i ; .s..A.. e i 4 m,_ p_4..,.- ,..r..--.# ._.c _,m 4 u. o. . i la a-__l _rl -l'_.:: .m! _,' W m L j' ie l ? I x + . i ..a l j

m

~ -~ i 4 4' ) >{ g h t o t i ; ;

1 i

sem

e _. W o Figure 5:. Affected and Unaffected a & p Floor and Outside Sedewalk Scan Results I; ji i1 213 14. i S i 617 i 8 ! 9 ! 10! 11;12 f13 i14 $15 j16 ; 17;18 l19 3 20 : 21: 22: 23 24: 25: 26 27 28 l29 '30.31 !32 !33.'34 l35 ;36 37 j 38 39 i40 + 1 i r i, = s > = r 4 e r 7 _ __w:_. g.. -4 a _A 7 _ _.r. A..g__4 .. - 4.-.p a v p, g._ 4._ n_ m_ u 4 i.1 a A.L

m. %_ u _ 4_u__

-r --- b-- r-t - t-5 a"" '* 714"" * 'c*m' ' +--+ T -- "t -mM - r =--W-- -Sudesunfk, Scan - , i, f'. . 7 M' 4 aun a se m scans M i A i - - + Fww% scans m- ) I ? n f + i t m (1600 clan m 2650 gun p scans q:., __{_p. j.....j< = $ 1200 epm to 2500 qwn p scans -- -+ 4 y-i --p-Q-H1400 gun h 1900 gun p scarm _, B ! ! } _,i_..

: . [

l-i ! i ' i A* i ! i ! I .'z y - ; i i ! ! l i. 1 .__ _ _ _ q _4 s C ! i ya t -_ H.1 L. A ._._, _.+ 4_~ z + -- _,-g z 4_.v_4___ +- g

v_N,_4 4__4._ o.,.%i N N,N NB N.N N.L %

+x _,% _+z,~+ _,y ,_.,_,.z 7_+DsN NfN N NiiNPJN3% v gq_4_w.A D ; i ! I N I N ! N.a.NT.+_N.N_ 4.N I Na _aw,dtKN. N N._.e ~g,_.,_,_,_g 4i i_ s V.NJN! VN: p k4 iN ._+4 .r4 4 4 _.4- _4 c4 - w pp 4 !s,!_ N N_ N N IN -M N's ! s N'N MN NN NN fN K NN NN N xiN NN NN NN fN NN N.a _ g! E N F j '.. i L' Njv\\ J -_J N...N.%__N N!N v.4_s v .e. - ..,i_O'd NJ..' +s.jNJ.'_J _:s _iN v_ _si'. J ' .+g N i ' 4 !N N_.jN ' g m s c 1 4_ -4 4 ~ + +. _ - _. G ' ! .N_ _.a_N _e,._e _ v _N..~ u V J' iN!' ? ? T J ? # A i V s N V

m. 4..._.._1~. v _. w.w_ v _. _ %_. %. m._d '.J4..a CN r s i '. :, T w.~.w +#.-4 _m'N LN NN w

H ! i i N.N 4 N ! ' N.a.N ! ~ N '.L.i d M_ y e +.~ r 9 t_ WN rN_..,N_%. 4_N.4__J.e% 4 4.+%+P ~ N ? :' X ! " B i N iN F ' N D. N n r F ^ !N N.3_ 4 %.- 4 _.g _ _.1 'N Ni .N N < ANN i%: 7..& wa_ a.N1N1, P y.P. !. NN P m s %# 4 a_.# .w _4 q I ! j {N-w.%jN __.4. t a d-.a. 4.w w.P s iN W i N f '-, 4 +P A**ded Area __.. i IN NIN i _.4 24 _N.__ 4 _ + _ % _+.wa4a.F_N-L.sp L_s Ap.m._ 'L i _.t %,_NI s a 'a N f ,\\ f _s. t s \\_ e.' \\ + +. 4_N ', N. s, .j - + ~ w +._ _p4.__,.+ ~. v _4_.., _.3._x g s -.:e %_+_.a_ _WW" s. e 4 m...- , _ r %.., IN N" t' s iN U ~_ K _ '..M[. - p.N .A '^^^" WWi N !Nr N P Th ' sWP i NINl g. .._ z. j i 9 54 L t lv N. .s i i x A-i s s =, _._<i.~4 _s;p i..- 4._, 4 sg.._,..g.-g., 4,_.x ;4.ms.p ..,_M V 1 .g ..g. 1- .a y i s :.., a ,q - u % q._ ,.. !NN: si\\j',;' _ ___ i _ _ _ - . l N__b hiN j X _ ! N N... _. j s ' 4 M ~m..+_. , _ :v ~rw g %.'g 4__ 3NN' % % _4.,,: N.,., _s ! - sj \\.f' A__ %. y.l\\psb _N. g. s.,j j P s 4 cp, _w= -~ + N, i !\\!N ..i' ._i, l' x f.~ l'. ~ s ! N w-3 aosaun m asoO en p=== u; N ! N. i ' ! \\ l '.-- h~p s s! s! M a=n m e ann a un '. -.w - 4 i.l's 4 .s -4.+ w w,+.w H ..m.-4--w w!N IN._r' N.!Nt i j' s;'. ! xonancwhen - w:s O ! l ! fdN +-. + 4 .._y _ _ v.~ v _J N N_ w.dy',.: l T._ J.1.L y. y N_ #y y xj gNj NWi ANNN [ fi .s _. y _u _. g'w_r % 3%g '_.4_ _x N_% _....g_.-. %4% s \\ (N, s ! i s com e ts com e, scans, f N ,u u -. ggs i n. e 4 t'

\\.',u _ i

,.3' 9g i- .b - 4 _. j i. s, s., i. s. -fb. . 4 -- d. _ :- 4. l.. '.p -. _sA .-e-c4 i in j N ; N. i ' s jN j i .e x, _s. i - 4 _.3 ._...a _,.t. .m s - _. ~. l.s.b. s..y -.. - si ,. -p s,

s s.

4 -.-g ..~ y - - h s Q ) Ni N i -sa N. J' N!1 l ~4 x si xf I' ~ d', N !Nis s ! 's i N .NJ.g \\_.g. - q-l s ._-.e. p 4__.. s s: s t s R i NNiN M Ni' = ^ J _M N4 j. J.._N, j N NN hpW N \\j N NA N N! NN N N N I N iN i M N N N N N+_N % J M NN Nj NF JN! .-. p ~_-j t _.. t_ % e_4._%__ s +4 $_ _+.- - w w_ + S . % ww % 4 !NJ.'.~s N.4__.A --.4-.x I 4--u; --4 I A-4--.u I w.- A N K. N N N %.-~N.NJ'JN p. mw_wrr A-wrI JNTN.+ bin.NjN.+ixi .i i N h. N !N IN -r L NN _m+,

r..

u-+r-u 5- +-_ ++ r L - w-a r 1-l T i _ a: m.,_ ' ~.

'. M.

,_f ^ i i ! .7 N.. c._ U i i V i i- ._...~.L i. p. 4 7 _. p _ j __ 4

a{

-- j..- . ;... [ Sseawak Scan j V ..' -l -.; 4 7. 7 2 4 com m od a=n a scans : - l 1 ' 3 i i-q.- - .i....p _ ; 7 4 u_ .. 4 p 3 - - _ e;. 7 W 1 i t _-4 4 g-4 q._J -.. + _, .. g4_4.%~,p.%, g w,.g__ ~% 4 .. p. 9.+ q - h w;.. H. 9_+ j 7_7 X i l Notes: 1. ~100% of the affected concrele/ metal Roor was scanned for a and S. Scan results (in cross hatched area) for a ranged from 7 cpm to 41 cpm and $ ranged from 800 gm to 3500 cpm. l 2. -100% of the unaffected concrete floor was scanned for a and S. Scan results (in cross hatched area) a ranged from 6 cpm to 18 cpm and p ranged from 1250 cpm to 2200 cpm. 3. -100% of the the concrete sidewak (foot print area) was scanned for a and S. Scan results (in cross hatched area) a ranged from 4 cpm to 84 cym. p ranged from1200 cpm to 2900 cpm. M scan readings were taken with a 434cm2 detector. 4. M concrete & pargal metal surfaces. 'l __ _--. _..~

W Figure 6: Affected a and p wallscan Results ~ i - i _....'q. < i 2 i 314 ;5 617 48 . I i1. s . ; = i : 4 9 i 10l 11 :12 l13 j14 :15 :16117 t18 :19 5 20 i 21! 22; 23.! 24. 25l 26 27 26 :29 '30 :31 :32.33 34 '35 36 37 T 38 !39 ido i. f - - 4 - ; _ i _. ;, u a %, ._g

,. 4 9 4 i _ p 4.. [. y _4-._,; 4._.

1. 4 _... _.a 4, _, L.__.#.. : _.q,_ ; _ g_ i,4_ a.._. L 4 . + . I I. i, ! .y t f f i 1 1

; i e

_;, 4 _ g; g). I a .. _... _, q _.q.~.... _+. ) i - i - [ __.? 1 p!.

o m s4 com.7_ p %,i_..., i_... _,

i 3 4._.4 }... - O m29 p u meAsces-T - A i 4 = 1 = + 1 .t - -- C-4660 @m W 1800 cpm p met scans.. _ h wi - + + g 5 m m gm p was m + f 7-d- -t--4--CH 775 cem m 1490 mm p uut scans, .es ecum : i., 4 i - ' - - - '. s i _l -- l__..!. b_._,. . A. _d._ L __. [ A_. I _I___. _j 4 d _k_ y... __...,_ t _ I_.._.j ~4,...

x. -,.._.w._

C t ? -.,t 1 1 e i i - w y.. _._.-..-4 4 p-l. v.-- O = l . J..A(p ' Y ? 'l'j $$ if [k. ' 4 4, % 4 S. s. h. ? U'M ' N N. 4.-N ' -} \\ \\ ' J D N h Ji'Mkw\\-VM u.\\ M [i.M ~ N O.\\ j [ s O.4'd Q Y M f f ^ a:MiMNiNiNi? iiiNN AWM.h[u\\\\'\\ o 4,. A,4v. w s *

Waf A4i & W:s v4\\h A @ MA%V4N b

E Ji ' ' i ' W'- Ny W' l - l - ._.. _ p.. y - _ +, 1 F 4 ^ e.a l ix i i ' - i ; l + , i i, g. A. ., ~ !... A, a. 7._ m.p ,.,_.a._,,._ p. .O x, I b. gs + .7 ,. _ 4... q,.. -.. p.o .._m4. - y _ 1_4 e, _.#4._p . p.. . A. _. p, e t i w G ! ! t Y 4....s. - L-._ ,4..1-+- - _ L 14., -- + - ..L _4.._Z __w.-4 _7._. y.4 _ yQ .s-s ~ ' i - i t 4 l t t 4 i i 1 ! JW t _L W a H s t -a i i A i, ; - i < l e e 1 .I 3 l s N., .p. _,4

2. s%-

t -4 4'...

7..,

3 1 i ,i e_ u. _.. p'...y _ _. L' u. l -) 1 ww . _. 4._.s a._ _+__ p._ g:._. i ' I. I l i l Asseted Area !

_ u...a

.. 4.. - 4._ % u i l C+ 'N' l ' i '.4-....A ._ h.. o _ p....+,, 4 4._ 1_ L.4 _.i__,f i _. _.4 -d _ qAy ,i._ } - I ~ ! i !... l.! NW .- - p. - 4.. '.._.,i ',,p -..J - 4_ ,_.4._ 4 2 J ^ ' _9 l' -t' q,;l l. _...i _,.. i.. YN 2 t { ) .4 . mm -w..: gN gg_ '~' M hh? HCL M IJ.4 aO6 ATsudIA W N W 4 6*r3 w. 9.u'.1TJ l q iO dp.mys mMW =1.. suss a -. g r; ( _4 / 7.,. ..y.-,.. L l. p. l... y _4._{. 4 _4.__ j._4 _4_.;._ M i 'ts d. D,c.ad N,.i.~ y m %.. J.Q._ W. i s' W_ ,.0^ xs .. s t4 2 4-m 4- - -- m.- 4 - -H H +,- +~-t~- 4 6' ~ _.ga N, i,' i, i. i, ' ! i i W = ' : 1 -. ._N,L.',.10 W 24[so cpm q =cens - P s eb eel e i +b \\ k. b+ + + t I r N... 4. _ _!_ f.. _ _... s t 715comm i usycans' C j N.w ! ! I.., tN ! i i i r- ....,.9..p .e 7 4._.+...4 4 _4_.e!. * !. g' ...i _ ms w Ama ' N; I

i j

I s O -2 l, 4 ' m,as.a mit ...p...i _.q p ww% 4 i j. l +} ! l '@{ i i 9, i L. ,--. 7 _ p _4._--

. 4.-

i.q q g , g _. mq_ P m, v. p.g._ 4 i. I ! l .s t s.es wm e m,o cyn p.es scens. _. - 4_ r

m.,:

u.. +._ q;.a.

..a. 4.. [. e p .4.-.,_ ,.n g 7.. I .p. 4vy 4_ 4._, Q j I i i sO' i e i i NtN g L_ i i R @ nWWx .Nx+ T = t m3 W WuWe v T .-t . _.. _ i.~!.4 _.. G.'C.C W x'4 W fiCi Q 4 % wegi..V4.N'.aV M Q NW.WW i-4 4 . f J_ .l.- l.--

_. 1.__ v S

BJW S.J N 'Y <i? i G M Cic.i' W Q $ 3? 3JQa\\.. ! ! ! ! ,_.9.._ T i r.g.- i i i ~ r. y',... r.., . p, i 2 . { g 4.. .]'.. .q... )... ;... y _._., u U i ~',. ..o e22,m. a scans i!

i r

,.- 1 .t y i.. i, 3, r 4 i , ~ 4 920 com b 1980. @m p =at scans = j ' i, i } ...m. i .I -4.4.-. t 9' 4 .-4' i. 7... 4--.f....4....+-.._,.-.A....j.y..-.4 9. h _. y.. -.n _. & 4 .-.4.. -..J..,_.d 4 F.. .y _ - p W = _._; - w _.y .n 4.- }. . j.. - '_4a I i ' :. i ._;.u. u, - i ! i e,.. p. j.... __. p __a 1_ .4.. p .t _ __-~ l. 4_.4..._ p._ p _.y.. L ._4 X i f j ; i ,m Notes: Ses* 1. -100% of the affected lower walls (bottom 2m) were scamed for a and p. Scan results (wi cross hatched area) for a ranged from 0 cpm to 84 cpm. p ranged from 660 cpm to 1960 cpm. 2. -10% of North, South, and East affected upper walls (above 2m, not shown on map) were scanned for a and p. Scan results, a O cpm to 15 cpm p 800 cpm to 1375 cpm. -25% of upper West wall (above 2m, not shown on map) was scanned for a and p. Scan results, a O cpm to 21 cpm, p 875 cpm to 1700 cpm. l 3. M scan readings were taken with a 434cm detector. l 2 l 5. M plaster, sheet rock, glass, metal and comert block surfaces. l I i i ___J

s ~s 7-, c w e. . r o A h> N Figure 7: ' Unaffected Area. Wall Scan and Exposure Rate Measurements-S4 v E 4 5 6! 7 8 9l10 11; 12 513 ; 14 l 15 i 16 i 17.18 l 19 4_.. + - - - ..., + K 1 e e 9 cpm e og seans, t 1 - ' ~ ~~ '

ll1050 e m to'1200 cpnt p wlan sdans 7 i

M "a* "a* 'a= 7 to 8 cpm a; waft scans -~ - - - - " ~ ~ -i "- +' 2040 cpm [ war scans. _(.. .a _ q. O = "a" P 15"

Floor-

.'58

u,.

O _.._m uw p._., 'l 'k 16p %, 14p h S

. s io s epm a wan scans -,

f~ T 1 ^ ' 1150 cpm to'1250 cpn1 - w'aR sdans ! 9. ^* ' ' ? i. r ) C '8 cprn u waH scans [ ^

~8'to 9 dpm 5t virait' scar'd D t

1100 cpm to 1250 cpm p war scans. 1650 cpm to 2200 cpm p war scans : Im W~5 Scale Notes: 1. -10% of the unaffected lower walls (bottom 2m) were scanned for a and S. Scan results (in cross hatched area) a ranged from 6 cpm to 9 cpm. p ranged from 1050 cpm to 2200 cpm. All a and p scan results were below release criteria. All scan readings were taken with a 434cm detector. 2 2. 11 exposure rate measurement (s) were taken.14 pR/hr to 16 pR/hr general area. 1 3. All plaster, sheet rock, and cement block surfaces. I 1

-. x _3.g.- l ,' _ f ' f I !4 m. .-l j ! l ~ .t { f.j .J.[4.,f l ga 44 444 4._.._! [ i.q.4..]l pk; 4._i_Lh,.t44_ 1 ,-. !.+t..e. 4 - -.i. i .-~,.n.. ^ .gla ;. w! _T.a _ wl i i L. i 2, ..LA a j! i l !_ _.7@. w ! ! i i U R ' ' i i g! M{ i ! I $ +._- 'L ~4 4i@!i%+! i a i 1_ l l i ,a $. _.r,_ - g. y., %. q._ __.4 $.p._ j . n..!.. ! 4, .t ,@l ? m_74 7 ._s_ ,__ _.7 l _i._ _i._ g L4'._-,. I... 1 4 i dh.,_. h A_.. _. p i E..._ !15i @i . u '. p.- i @i ._y_A_ s..i

e. %-,!,M i.-

s 2_ 7 i i .. g i 4 l g: -v7 .~ 1 3 ... _.g L. 1 _ _. 4.. L. .4. -.Q.4 j .l.. 1 .4. _..i i %.I' !@- p ,,a .p'@.-.r,J i. ! _! $y. F._...I. _..,.y m L! !,;__ @!. gL' I-7 a._ l g! .t i ; i ; - i +.+...u-7_. --+_ 7 - g. - ,-+. o ..g ! -d. ' -{..- .R f..@l. .. i.. 4.d

! ! i

4.1.@.i ~..+; R l @i i 6 ...,y. 4..% +. .y . I I _v.,. f i i ! l E -- 4 .p{_ 8 I l E {5 g t $ e. 4@.Q... j;,!-. l 4 L 4J .$ u._ 4.4 y i !@i ..m -.L..i @x' L - '.-l i.. g g ,e ...1., [ h ..L }_ i._I,'i- _dg.i._.i _.g gg A ...b. .e n!, L,' ~!..,._ %.I__@i.l R i :@ l-7.l@le.IL. @,! ) i i, - ~, x.. t g l 4 _..p,..+m.....,_ g.g..H....! 4 i _4 - p@..y_ a: i t i 4 u c,_. . _ +. Nt ! y n! !., @...(l 5 J,i@! i .= 5 j t.-7 + ,) ( 7 g. _7.., I ! 9. p.. _ g.1. +.,! t t l 4._,.. i 1 .u.~ ; i _a ! .u!._ g @ i.4,ii %.q s +._ -.p.. 4._._4.-._ - m@ i 4. p! @q... ) e* .i ! i i i ,,l.- r r 7 .r zi i I i i ! I i u i =

' 4, 'i-

= _ _ L. 4 q _. p.. 5 j@i._y 5.- .$ {i... ,_4 ' i

p. _ f -4

. -. ~. -. @. i. _ .n!

I

,i p. . _ u, -~ g .j .b d _.T-'

~~ i-.%,',..._~

@. "f_.. .$pl" ~ @'~_~l -' p~~'g: @'..-

4. $+-~

@~ ! ~ .. : i,,. g g '7 ~ ~ I '"t i )

I

,= .+ _.pp. g 7 E "4' ~.M'. 4. _,.d_ ga E' I h L.a. .L j. _,,.%_..r.d.-..+- -.i - g "1% .. ! l.- [-- @l _

@l _!

-" 7... ( g] E t ~f y i .L zia 4_ L n R g %u @l j$w@_!i.3 i@ N_, L [.__h.._.'.y I ! l 4

~

1 ... ul@L1 L .L}.a} -.1-Li I. J g _. 7 7..p 4 1 l' l.i._i_..L _.L E 8 g !.1 r l $7f j - -~, l u.+. t i ! i ! E ~ q y.-. ~.p F-3jg. a-

77. rp

} z..4..L.L p-L# y L -. _v, ) hgj * @.jlg._i_$ii, @..I i !._i _ L + t o' -p ._. y. 7 I w Ot i t t i i i I g a t M -t r L..I._._a'.,. $,-. i g ~r__;._ A. i>

e. 33

.e-e

i 8

1 a J. 1 ,e v .a i ! o, 4 q...r. 1 ~ _ +. -. %. 4.. 2 g L- .. 4.a .p _.,@,_ i i @4.g.i,i ._...y@

y

-~, n : L.- i $g 'g i , 73 y.7 7 23 5 a.._ !..-. _._!._

4 t

t I ci l l. 0l !@!.,. 4 @.. . ) .i 5 _m_. .2.2 i 4,_... -.m i i ! eg g4 _.4._,_._._.. + 1 -4 m. '._. 1.. ! l_ !%ad._,i_.i j !

g 3

.I l t _.1. 4 .r... y.. a g ! l _#4 t ' i ' i i, 16 !.. !.r. -. i ) E. .~._.'.+ n!.-.l - - - - + e ~ _ _1' _%._.4_..;;._3....p.4_ y_4.._ h .4._. = u e .i . p a._ y - +.. +. 4_..,. .,_.p.+ da l 5 ! i i.i ; i : 1 = 4_,._&_n4m. _ _u _ -. w.a.~h.g e..t+_v. n

n.. -.

..., + - - _,. -. ~. -. - 1 .i., l.. 4 t 1 m % + _.3 .w..+.-.+.. _... 4.._

v. _.,L.4....

} I f i - i < l co l o l o ! w t u., { c II !-- }m ): L2 !z jo ja. jo j cr j u) a. p 2 + M (d gsj i : i B, il: j x e i, ; ; a t

0-A ht N Figure 9: Unaffected Area. Fixed and Removable Contamination ResultS S4 V E 4 5, 6f 7 8 9 l 10l 11! 12 ! 13 l 14 i 15 ; 16 ; 17: 18 ! 19 .. +. _ t .-K. ,__J [ p... ...._ p..- ; _ L wk en wn wh 4 _ M W '"? W u

r ***

a q).... j... u... L. . gy ~ N oy c. _. 4._...a _m O

n.

rri ,,o 4 1 Floor. .. u,.. ; t_. 4 u.+ 4 a, n, e p..._ - w. p = d -- i **" Q 46 .a -- D _ t. _ -4_ J .... su. - O

won

,,,, y um,0 -t-hp m , tu }. g. 5 - 345 - - & -- 4 - Noora -- + - ~! M .t e's db O .te9 .. * * " _" ' " _ ~ S i i _.- T 1 t .x -.... _ -.. .p. .g..,_.. t i 1m Scale Notes: 1. The values provided are the approximate locations of measurements taken. Two minute (cp2m) fixed p readings were taken 2 - every 4 meters (total of 18 readings) using a 100 cm detector. The maximum results was 771 dpm/100cm2 2. The numbers circled are approximate locations of wipes taken. Maximum wipe results, is 13 dpm/100cm2 & All a is <10 dpm/100cm2. 3. Overhead (Light fixtures. *1" beams & ductwork, not shown) structures. Wipe results, p is <10 dpm/100cm2 & All a is <10 dpm/100cm2. 4. All plaster, sheet rock, cement block, metal & coricrete surfaces.

g. Figure 10: Exposure Rate and Pdnt Sample' Results 4 g ,. i ; 4 i 1 r it ' 2 I3 I4 !5. 6 l7 i8 9 I 10! 11 !12 !13 il4115 !16 ; 17 :18 } 19 ; 20 ! 21 ; 22 l 23 " 24 ! 25 ; 26 27 :28,29 :30 '31,32.33 34 ! 35 '36.37 j 38 :39 40 i 1 _._. 4 .;. 4. L_.- 4 _.p w. ; ._l.. 4 _;

_. 4. - 4 a.... v _ r.%. _1 ~-. ;4w 1

_4 _. t _..
__.4...

4.~_,#..~.._4 . _ L_. gl

l..M _ -. 4..i. 1_._1...d

.. _. + d. _. _.[_ q _

1.... 1 2 _ 4. _. 4 ___ _,...k- _

4 _..y_ y._.. __ h._ j_._l. 4 4 a'2 ' ' i -i i i i ~ ? i j ~ j i s . L._.d _.h_. u. a,l + _t.14. p.i i ! ~ ' 2 . i !. ! ~ ! !. I ! l-i i ' ' i - -+_q w. L -. L.4 2 ..-.--_u 4 _wl i ! ~ ' ' A 2 B i ' .a m -.., x 8 = L. z 3 - -. p __w w2 D ' ' ; i i

i

! i i ! ' ' i i_ _1_ p. g 4 u p. p2H 4_. 4.._4- _.p, _ __ w;.. L ' i p._!. 4 , i _. y... L ,._.p ___ _.4._ 4 __q C : ! a. y 4_ ! _4 i t i r . ~, ...r. -n._.+.- D ! ' I i i i l. t , i 6-

. _ 4 _. r _p 7..: i. _. p.. '

i i ; + 4 ..p.. i i i, 1 i r @AE ,a , v_ r_ . 3).i( 2 ~ .a....~~..~, .+M..u. .. w_, m ' i n. 3 E : ! i ' ' ' ! i i ! F _"5.. i ;

+

= +

ne ya i i ~ I ! y+% .a + =+ ,n + 5 4 _a __y e p. t n+ _a. L +m.__ ._ _ _ _ m. m.. 4 G i i l ! ' 2 m _ p p p.g.+__ s _j. pl 1 i _._ 4. _! l ! 4 1 .c. 4 . -.4..q 4 _ t. .s _ _.u _ _. _..: . p.-4 _.t. _ _ p. u m.4 H un pn un ~ un un kre. nn un un un ! .u n ; un _. ' a _. + u 4 _u _p u _4 4 -_.;._e,_ ua _m.a_.y a A_4_ ;g :a g _ _u._ t t . J... 4... _4 .L. 1._. !pL._.-4_.p,t -p A#scred Area ! J_ -.p.a _ _.4 _.L y _.4 -_4._p._...__4_. -,4 ! 1 ! i i i ! : i ~ ' l 1 .; j .p 1 was i i 1 r ya i

..p._

J i = +_w3 e >. m. p__ e= *p._a 1 >= a ' ** j *+ i

1

=* a+ a _.g. 4, __ ' ' i.._., _ _ _ -1'. . %._t_ t. 2_- t_ W- -- e; ng i,

t,

! - 1 dae ; K .--.l. L.. ...l. ~ f J., ~ "u M E. m M muurm.. i .. em -- -_.. cgfg y= _ _ gp. & _. - war l,- l l

Kh t u FW d wa0 d

-h+"-yars----,_ _4.J 4 _ __1.,,42. m_.4 a -5. 4.-- ; -....Q -p._. ---t_ h-. !l

~

i l ., i l 1 .2 _. a _ a__ _,_4 p_ .. j . _.p._. _.ha M i l . W . 4 -.c.- %.~ m _ b 1R[ ! ps i 3

ae

j i
e a+

N 1

r..

j. j i i was

wesed ary l ; i

(. l ; i l O i 4 i P 4.o_ -.. r 4 _p e _e.._t ..._ _..m._._- _ _,.+ w, 4 u. n.- f i um ; se ' A '

- i ha
- i ne

- r. 4" _j 4._4 .4 4 g,._4 . M.. p - ,.2_

_, a -

r.. .2 -4._- g ____+.; .._7

h... _...

O i i i i i m 1 i ' ; i i 4 4 . + [ N e , i i, s R t ,i a, m 3 - 4w-w' as 4. - ,n 1 . n' I i I i s i i i v . a _a' _.r 1 t n. ~. - ~ - v--+ ( .+ _ ; n i ! i ^ + t S , l ! -.y- ,.w 7.4_ , a 9.-. w -n-I ,.. 1 I ! I j > 4 -{ ,,,= r woocmtsgwr,% w 'j + 4 ~+ 1 T-U 1 t @rW100cm'Merpaint was removed L' )'. .a. u._. ;

i. I

,I i a-v . a-i m. l r .~ a- +.., + l. i. { W ~ +_. r - _m e._.__.-.

. 4 y

_.m _.... _ m ..m-.-..._4 _.~ ~-,, r i y 1m Notes: 2 2 1. The numbered diamonds are approximate locat;ons of paint samples taken. Paint sample results, Maximum $ is 251 dpm/100cm & An a is <10 dpm/100cm. A total of 12 paint samples were conected. Al paint samples below release criteria. [ 2. The values provided are the approximate locations of measurements taken. Two minute (cp2m) fixed $ readings were taken before the paint samples were lifted and a two minute (cp2m) fixed p readings were taken after the paint samples were lifted. A total of 24 (pre and post) measurements were taken using a 100 cm detector. The maxwnum results was 290 dpm/100cm'. r 3. 57 exposure rate measurement (s) were taken. General area pR scan result (s) ranged from 15pR/hr to 19pR/hr. 4. Au concrete surfaces.

w .S N Figure 11: Sidewak (foot print Cres) Fixed, Removable Contamination and Exposure Rate Measurements i - i i. 3. !5 6 ! 7 j 8 i 9 l 10 ! 11!12 l13114115 it? l 17;18 !19 i20 !.21 l 22 { 23: 24 l 25 ! 26 '_27 28 I29 30 i31,1-r 44. a -.. A. .4..- I j l1 ! 2 l3 : 4.

i s

z

i- : >.,. : i.,

32 33 '34 I35 36.37 l 36'39 2 40 { ..y-..,..- + .,__u 4-y ... y.. +. _. LM _ q.w_.24 au _1 u nu_4.._% _.n..m.t_.i_ umu_ v p, a _ _. 4 w..J. A _ _ Iii! ! ' i j 3 f I ' A i 1 1 -. p._c_ _.. p._i-- p. 7 _L. A.qw., 4.' ! i i ? I 1 i I p. LL_ Lq.,!.. 4. 4 q.. 4_...q _.- 4 44. L 4 4 pq _. ' +q.,q q__14.-. i. p. i i i y p. ... y _ 4 _ ' i 1 - i i i i B- ._4 i i s t 1 s t 'r i . q _ } _- w q. 1 - - '..-..po t - i , i t i ,4 5 1_.#. f i : > '

1 t

5 .{ W.-,-.-~4 i 4 ,t ,...4 4 _ _.4_ -p. i i i - - - s_p_+..- } - 4._ -+-v.. '._.-_4-_..-y_.L._ -t.-.&, c ; i 4 *i~ I' ' = I r r,' - L ~ I r-a ,I I~e- " * : m I 4 H e

> Ir - -: i,

I ~! !,'4. T 7 t : - 1 e i o . e ; ; ; 17,Rn, O .te,nn, O =g_e.,! _ r., i

i.

O 4 Oi 17Tu. t_ %._1 p._. te,% a .. _ ig% m ? e a _.. . a m-E l l 1 += 0 0 ' i : += i . -..._ } 7 F t i 6 i t t I i i q. - 4 9 4 - + q.. 4._L 4, u._ H'-_4. q w q._ p. 4'4 ;__L._ p.4'_,._1 _ p.L. A Au i 6 i ! I ! i ! i i ' 4 i _ _._._. L,. ;.- {_ ; _L i.i.~ L [ _L_..L j_ p' G t 4 + L.H._.4 p.4 ? _. L-4. - H.;i_ A L.H _._.1% %. j- !.. - t - 4.. 4._. .. p. L-_ L.]! - t .p.L'.w.,! I }, 1 H

.,i l

?* w .n._ _.,! i i _. ~;_ ; i, i.g. ~- . %_.I. _r. y_ m9 I I e i r 1 . r i 4 t I 1 l j i ? i 1 i l' ...~ i j I'

1 !

. e. y _.q.+ r j-m-* - &{I 17pRN i i i H-- - - M-- * -- -t--- +!--- --H'! t " r - *'-- -- P T - & t b - r --M - -- i : :, .._.r_3.., p1 -._ g. - + " - - -. - I i _ g.{'- p.# L_.p _ _.H _- 4.-..; i i ' ' ' q4._ 4y ' _ %' H'_ _L p p g i_ O _.; d L._ J i y'_4._1y;_ i ; 6 I r K i ?&R* l. i : i - t t i ._~4_x.q-....~. w._.- - s -., a.a. { l l f _ +; E - ' E ggg _... y! !~.... L u ._ i4 L1 L p._n_ p

4. g,

_qu _ R _1_ p +._p qw_.4 _.4 . g.; u.... 7 eo

i i

; ; i se

+ 1 1 1 %.--+; i.. q- - - + -... ___._-e__4_-

_n

__i i ..~ _ _. .___.9 !14m t i = ! .r C,m g_ i __ 4 _ _'_ 4. # i - e - g L' g____i.__' i i I i i i N p.4y! + ;!p.. n _r,l ! i

-, q!.

u.#_ _j i ' j i ..a _.m.+ is _+ m-i.-/..!.. l i_.- O i } 4,j ; ; ; mascswAres l ' 1 -.,-,1..n. 4 n, -. + g. .,.- _y 1 p l ! ; , i. a_s i e. -. i

i. l i

+ r f.-_ % +_.,4 4 - i = - - i t ., g_ t _. 4 _ + 1 s. 3m _ + a._ u -+ _.a

a. _.-g o i ;

w=0 1 ! t C,=,w_i, i > i i

i i ti ~ - ;

- : i 1 i _ _.m e. u O,.. m .. O _.., y! _.-,O,_. i !_.,O SIChEWALK, R i i l I _ ~ ~. - - .. ;. _4. -, r_4 ..1 ~,- -,* 4 r j 16pRtE , j 14RMr@ f 16pRMr ifpRMr j 18pRhr

j.. - _

. _.m ._._a. ~ _. S ! j 15pRMr 14RMr @'.14. Rk l 14Rh L '-- 'l I j 16pRhr 14W 21p% g a_. -- 4 2I "r' -- ' - - r -- - - r " " I ' ; - - L I ' ~ r -i- - .. _. _. _ +. 1 [ .._...i 4.... L. 4 4.gf. p i.- _._.f _.q.. - } - i L, ^ m. 4 -. f.. {.... '. p. h ;..y - p u -.. h. - ; - --. -._. j i-t 4 i i ! ! ! i t 't U l l 1

p +: - >

s.. ;_ .[ p.e +t j e. 3 .._a._, p .. p. +_ _, 3 i

i i

y J. .i _ :,....;--.. [ i j l.. 4 - -+. '. _ p... !.-. 1 .L._i__ i. L.L +.4.-.J[_ ; i__. -.L _.__. L. _ [.. ? . +... + W ! l l.. { ; ' i ! ; i i t ; = ! j 1 -.. _( q - y. - - 3 + ... r, -p m.. --g. + -m, _. y g _, - + -+ ~ w n. w. 7 3.n.- --q. m --- )( 1 t Notes: Sease I 1. The values provided are the approximate locations (square boxes) of measurements taken. Two minute (cp2m) lixed $ readogs were taken 2 2 - every 4 meters (total of 26 readings) using a 100cm detector. The maximum results was 771@m/100cm. AN measurements were below release criteria. a 2 2. The numbers circled are approximate locations of wipes taken. Wipe results Maximum $ is 10 dpm/100cm & AR tr is <10 dpm/100cm. 3. 31 exposure rate maawement(s) were taken. General area pR scan result (s) 14pR/hr to 21pR/hr. 4. AR cx)ncrete surfaces.

n r - m ~m. m em C. r~m

v..

r. a r~t r-q,ym e r. 1 m _ r O o . Figure 12: NC & Heating Ductwoft Fixed, and Removable Contamination. _E t 3 3 = 1 2!3 ;4 5>6, - i. . i - 1 s 1._. L. . !.i 7 l 8 ! 9 l 10.11:12 ;13 !14 ?15 ! s6. 17 !18 119 : 20 ; 21 l 22 ! 23 : 24 : 25. 26l27 :28.29 '30 :31 '32.33 34 35 :36,37 i 38 '39 ido ! r .- 4 _ _ r _ -. ;_ .._'.a _; w... L. 1 .m +4 .. _ _ u .r 2 ~._4 _.1. .4 f ! I ! { r I ;. l-i ! l i j j ! ' l-l - t ~ _ _.;y + s t 4 1-u w..p

..3- '..t _ # _ _

. _ p.2 -- - 4 ..~.;._.. u ; a! w w ;_ p_; .._..~4.o 4 ,-). 4 ,y i, ; i.,. i _ i ; _ j.. [. -. = q-- p. - i ( i, : A l l ! ; 1 i i ** 4

i j i a

..,1..-,.. h...+ 3 ~ B ! I ' ! ; j i i l

~

...-g r 4 W,w-,-... i f 4.-.g..6-. -...--'t*-"I-4 - 4

+-~~4'-'

C- k--P- 1 i ; I i ! ! ! ' ! i i ! i '4 4...,' '. h..- d. l k l k ( i -4 -, 4- - -h.. h. i 4-..4.. ..a,... d b.+ 4.-y .h ., f.- 4 . 9. - h -.4 -. I _,.- I. -.~..h..,,. h d.

d..h'-_.-.[.

~ -6.-~+,..b. Y f j l l I J I f 4 f 4 y 4 I, + ,7 - 7 p._.-.p I 3 I.. + %-- ..L. I -.w_4 I y-D.,.... =. -. I,, - w. .,,. ii i I i SIDEwALKt - I. - p_i -. 7 i i 9 I p p ~lI p q_j _f. I,

-I +

ii t i I i i ! i .+ -. .e.-.% - -.,a. i f i l i ' l-2 i t i e e-3~ .f w g.. F i w.p., 4 4... g.__ .,-.h,.. '. ~ 1 l '.~.d-i i i ..d.--...&-.%..j i t i i '.-. -..,..-.~.,.

j. '

~. - - _. - i i km .. h. L... d. -.4- ~~p..- --.q - - h M- -- G .,, -..i.. 4.~.c}% .y ..g-. ~ .-4.4.. 4-- m-. --p..H..,% 9. ] - t-. ~ew4...]---..,d-H-i i 1 i

- ~- + j. - + - -

i -.6 l i [ ' M{, ,.. -,p.-

[

+ q.. ~{ . _ ~ ~, ' t f a .r.-... -g l -, I. - .,4. - f s-l l l l l I ! !.+.-- 4~.w[ --, l __ _.u ' ~. h .,..-..%.+.! l l l i, ! ...L 4.. .g. s. ~ +., p..,.-.-y... -. 9 .s 4 4 -.p-- c .4. g-e=-- h.u .6.% g. 3..m .,-,...-e i-.i---- -.1 n 7--,-- -,. - 4 3 -= c .--4 a.%-4.-~ f_- K k--- t A % g, m m m _ _____. _ __ _- a - __ i i 1 a_ym_ viem%j%pAm=__e__m- -. - ~ - + 1 t .n _,=m t-r v, --} r7- _ _ = - -

i

12 i,

.: i_ i., _ i j _pL J M l l 4 i i ~ ,,l. i ij. i i mm,~. -4 p. - -... h d.,---'3 4_ ._4 5. .a _.. i i .- h a u.~! .a.-w k.- -. .a. ,. h. .L. -h y. L.---h-----4.--- .,-4-- 4 N 5- _. i, i 1 -. n_ i I + .i as_i i ; i i l i i -a... , ww O { unamecrepea i i ? i ! .>.a.,

! ! i.

v a.-. ._. w .+ 1

i k

.. + + .- 4.--. ,-L.. .-.d--- -- --.+ r 4 -.. ~.. ~...- --.- -..+- 7 ..-w - +- - +d-.- P i t

4. a _ ~< 1 -_

_f1_ < i - !. i i ! 4 m % L. - _J' 4 y.- i. & 1-l.~4 4 -.4.._m Q _, l l i ' i l l l . a_ .c ! i i i ! 4 i ! ' ' ....-..-9 -4... 9 9 p. ,4. R ' i + L. p f' k'. -. L_+1._ 4~. L.d.: .d L [' __1 1,_.p. 4 u y'. - t i l i < ( l ' l i i t i a i i ! -4 + i i I 44- [.~ . ~ l 4 4 4 4, b._. i_l - b' g - S -.,., ,_i 4 r 1.,_ L L L. i { f ' i ; i ! i ; i ! i-I SIDEWALK! i i i ? i i i I, t ! ! i L1 L lI b1- - I MT L 4 I b' ' - J p. LJI' LIL u -IJ-4._.4I.d_ L L 4-I 4 i I-1 ~ 1- - T I i m 4 4 ' _4. -. .,.. 2 - t .t. 1 i. ,i i j - + - .1~ .+m-4 _ 4 U +. t i ~ i i r p - ; i 4 , - 4 4 , + - . i' 4 ..-.4 4 r, = i., + V 37 4- !.i ; i 4 1 4 ~.. _ -4 .i. .i. 4 + _,...l g q....g - - _ +.. 7,_m VV, 4 _-._.1 . ~ ._.4 i i t i i

i

_..y. y .- 4 a- - e.. r - - - r q. .y - 7 - X y 1. Large area masskn wipes were taken on the duct work. No p actmity above background was detected on large area wipes. 2. The values provided are the approximate locations of measurements taken. Two minute (cp2m) fixed p readings were taken (total of 25 readings) using a 100 cm detector. The maximum results was 479 dpm/100cm'. 8 3. The numbers circled are approximate locations of wipes taken. Wipe results. Maximum p is 21 dpm/100cm2 & Maximum a is 77 dpm/100cm, 2 4. Flemovable Contamination survey was taken intemally (duct work),7 wipes were taken. Wipe results. All a was < 10 dpm/100cm2 and M p was < 10 dpm/100cm2 5. M metal surfaces. m-e

w Figure 13: Sprinkler System. Removable Contamination. _E__ ! 8 ;i 9 1 10i11!12,13 ;14 (15 ;16 [ 17'18 !19 :20 ' 211 22: 23: 24 25! 26'27 '.28 ;29 ;30 ;31 ;32 :33 34 635.36 37 i 38:39 140 i ,1 2 l3 !4 !S lif'7 a 1 e e r e 4 , i,,.. t z r e ! I t i m -L, a _j-4 . k.J ^

i. i ; ;_+

j i J.. L..

i. ; }.. ?.

1 .4 _,_4 .. +., _. ' i ; 4.

J.-. i i.....j..

t =, 4 I' ,i. ; .p_.a._.,' ..i i i t t

i

..+._i e 1 4 .4 +_ -.i ~+.-.4 t_ a. _ t_, m._... ., p .4..;. p....t... i j ., +.,. r_... ~.. _ 4 . a...+__ .+4.. ...v._4 ~ ' t l l i i : j i 1 i A l j ' ' 4 4 4.4 _[ ._L . _.1, i -,i - f.. ' I_.i 4._ f

1. -. L _

.3 -.1 4._ q. - ;._. _ i --.. d _ _. ?, __. h. h. [.. .j-4 1 .. _.B..m . 4. -.i _ - t _4 . ; i. I.

i i

i I' i e

i r

.I i, ~. ' > ! i ,i i ' i .._._.2_;. a o._a--__. s _ u._ a. q _ e L _ 'v w-~ . - ;. - _, _ - 4 ..i i i j i 3 ' i ! i ' 7- -.. _ 7. _ e.

p. _

_4..a.._.~.-. 4.

r.... 4 - _.

' ' i i ' i i e. C i _D.... i ' t------t--------4---+-4-~~*+-4--+ - - - ' + - ' - - - * - - * --'4 -----'lt-'; '-*i ! ! ! l j j s s - + -- 2 stDE' WALK + -- - i-- * - t ---- +i -- - r- - *! '-~' - -"j-l ! i ; i ! ; ! ; ! 1 ! -}-!- i i ! I i t ) E ! j [ [; 4 . j

.l_

b4 ~.4_4_._4 1-.4_J ..,.#-.~ p_4 -._4 _ p..;._.4 4._ 4 4 _ f._+. ...__4 w A _p-$. _ _i... i l i i

;. I i. ! I i l' i ! ' l i

i j.1 - l L i i i i d .. G.. _4 -4. - -.7.. _ j-__ E_ 4 _.+.._w. _.. + l..,__4 _ L.i. - - 4 _ 1.. _4 _- --i - _a _ _. _ q......,-. 4, --. _ _. - _.

i M i j ( 2(_.

l

Y.

i i N !==(30) Al j _ _ (7 ) +.. _4._ a i, ._4._.i.%.- -q --.._4.w.. - j rl ' f l i I 3 j [ ! I l, i m --. 4 --. 4.. -.s q-- ~. .{ _. ~. _. 4 4._4 . I _.- 3

. _ _ 1. 7-- y..

.-. _.. j... ) -- p.. - _4 -. -<4 l u..

i a;

I l I i ! e w..!.__+i.g._.-.- y!.!. ! ,i a. ,1 i -9% _4 w.+ ~ . + - ~e... 4 -. U f. _6 -p4 + ,.E . K. ( ! i, o i i

i..

v__ _ ! ,, i. 7 4 -4 ~ 4 u. . _. +.. .q._. .+_-,.L.. c- -p.- 7y -p [., i t i i i l I f l Affected A4a ! i I . q _ !.... .%_ 4_. - a' L. L. 4 _ -.(: --

L..

_4 ._4 . _. + _j.. _t y ' ~ M l t

i !: i. j i

i + ! g. i. 4 -g r J N.. 4 _.4 .+ q. 4.. a -, - b. .__.a _4H -. + - vi i 24 j i I-4-_ 4_ k_, 1-I4 .-4 23 - ! i j - r _.. t -- 4q _4- - - L 4. -- +-.q - _+ _> r 3 . l O... - j ' unasecreverea !_. _;.i ...a - 4._.+j.-,.---.. 4_

w. 4...

4 .... ~ _ ;-- 4 [ i P m._ t 4 -._ g w.-r..+ g,%-- _ _ge ~_, =! i i i ! i i ! i j i l 1 Q l J + i .R m._J 5 21 20 19 18 i. } v V -.l_ ~ -o.. t.. - t i 5 i : i i t ! ! t i i i i i 4 ~.4. _L Q. - _d. _ _4. _ _ _i_ : .i._.. _-.-l._.j_? M S/pgwALKL- +l--y-LJ_j-y- .--+d -p!--- -y w r i 4 + t i S i ! ! } i : ! i : l i ! i

i j l -~ 4 -.J-+i -

-a +- -.+ _.i. 1. _4_._n ._._2 ~ 4_L.. 1 -. j ; . I . i _ La.a .t . l. L._.2._ +._a-d. J ...__3, = 1 j j 4_ i i ..a. i U i. .} ..i + i V t +, 4 l ! i ,4 t .._.y. . + ...-t. + _. _. - e 4 a_+ + r 4 W i ! i ,4 2 4 _.4 _ +. -... 7 - 4 X Scale I Notes: 1. Large area masslin wipes were taken on the sprinkler system. No p activity above background was detected on large area wipes. a r 2. The numbers circled are approximate locations of wipes taken. Wipe results. Maximum p is 41 dpm/100cm & Maximum a is 17 dpm/100cm, 3. AD painted metal surfaces.

W-Figure 14: Overhead T Beams and Lights. Fixed and Removable Contamination Locations and Results i ; ;1 j 2 !3 j4 ls 1 e i 7 j 8 { 9 ! 10! 11l12 213 j14 l15 l16 { 17l18 l19 l20 ! 21 j 22 j 23[ 24!_25(26l27,28 l29 l30 [31 !32 l33 ;34 {35 36 ;37 j 36.39 l40 i j l i _ _u 4_ ' _ i _. L2.... _&% #4_. 3' _ +! _,__p..,_... _4 .#- y _ < - _ _ _ -. m ' ! ; ! i .w a _ m _4._.m w _. u. % I a. 9 a _4 %. i. -4 ! i ! i l a a _,}_ x._i l-t t 44a+:i i i 4 u;_.a. 4_.,_.%;.c_.+ 4 _ L 4 # J. A na.~ l ii i ! ! ! ! i 't 2' i A : i i i i._ L i i

~ ;

~ i i ,.. 4._. t_.i a! J __. L..x 2 ._i 4 i a!.i_ L [.J- {.24...a._L J_A_ :..a_.4.L ! t i 1 i i ! i i i ! I .4 1_ . _.4._. 4_ - _4 4..].-. n.. L i .d ... d .. h _. _L .a .-.)._ .m. r 4- ,I.,_,_._.,.y-.y,_,_ qi..x +---- z w p' ~I - l z } j j._ {+ ~.-. x{,- l p-- z - - +.-+q-r M.- - -.+-_ t.-.4 z - D i o-l 1.

I i.t !

l StoavALK i i i g. 4. __m s 4._ F I t i i - r- }._4._' i .i __ } i u h' - p_.l.. y ) d' M.. _ j L_ J i 2 .-.... L... L 1 i 4_ a 1.__; M 4 4._.y 2 ..- ?. 1 g_ ~4., G, l l l -l l .I

l

_.~ q_. _ u. 1 _4_ _9 sq.. _ .gl . ; j i 1 l t t _. _ r. __gl. 7 q

4.. _ p q

y, pq _1 4_ 4 H j + } } } ;

j.

7 j I y j j_ j.q . ; i. u__q 4 o r _1 - j i 7 _7 7 _.g. s. L_ 4._ .p.1 ;_ y2.., ,a E-__ L. 1 J _... 4_LL L a.- _. ~. _ : i 4 a L. _. J ! i : _a - j ..~ w l j< L,i j j1 xl i .1 i, x. a.- y .s n., K } j j l ; j _.L... ;. ! { ; j ! l j(s) i j(s) a! 1 -t + ~;. _ m .g -._ d, L ..l s._ .--9.- _.t._ + i -. _.___.2 a + _4 ., _, + ~ i l ' i J l i ! I __j l ! l ! j 4 1 . _.. j.~.- a.. -e q -.7 l lq_ _p AAlecte4 ee _y-_r.. p _ _ t-- p g }- %.._ q -_1-. p.p._ p._1.g .__.p... q u! ' H. M i t i, t-l !~ i i l-4 M.s _4.._4 -4_.__pl p. i 4 i ! i I i t l i i L.4._ >. H -#q. N _j w} + t ~ _9 !._ 9 .__.3 _._,_i.._ ;7 i .' ~ _.i. +,

{ l t

.t i

}

4.,... p ! 1 .-.L.4 4 w.i _ +._,... ..._.u._. 7.q - _.. r ._;a O ; ! I obaected Ares ! i ! M 1 I i< ! ! N 1 ! i i _. p<t -.9_- r d*)_~ H _- i- _.+,._ '! . i + _-P. 4 _+ _a w. .+._4_a a - L..L. k l. _ 1 1 A.. !_L_ I _4__ 4 ~..a _4a t J i l .gl p i { ! I i i p l i Ei O. _. _ _ _g.-,

p. 4.

_s_ 4- -p..,i._ 4 _._. a q_ % 4,_.. ~ p y,,m p y - 4 p! i i

i g.g 1

l i, ! i : ! ! i 1x I _i ! .p-. ~LH e r R } ;, l d i-t t 5 !i 1 ! j.I c-p..m[ 7.j~ _._1.q; _' pL._ j.+}. d., pl _ -li. J '__.1.+._ a! l5 i-i r lf.4 4 4._ +!_ i 2.. 4 q}= L_4 r a_4_ j +T,__,. a.~ __ _ r S ! } } ) }.l i ! l . t -. z l_ L_._a; _.4 r. simmLK i 4 _ a r.._ _+i__.4._ +l r - i_- 4r_!__._+~_ ru[_.2_ 1 r t.-*i _ m. l- ~_'n r. p -j - .._4 q. .p - r I 1 ,i_., _ q _,- %.. I 1_1_ _ i.._, !..._ p, ,! _;l... _.9.. !. i i ; - 7 _7 m... _. 4 4 y , - e. - g u 1 i i i , i ! L. m. q _, _.,, _4+ 4-.5-i. J-p, 4.p. _;_i r> ' ( l . i _1 1 _ _ _ J _. .. t m.- 4... 4_ 1_ + i - e.2 - + m.. -., a V j JOverheadUghts) j { k l } } i. i lt ^ p..j j ! l [ -. ~;-.}- ~4.- a . i.- b' W_.. _._ % -, + s a......_ 4 m -_4 4 ..y 4 -- ._ L. .. e.4 - ; ,_.~_+_-,~% 1 -..+ i j i j i i 4 _ --_v _.p +4 y-4 4 ~ ; -p-f q - ; i,_ ! !. l i .-...__i X . i Notes: 1. t arge area masshn wipes were taken on the T beams. No p activity above background was detected on targe area wipes. 2. The values provided are the approximate locations of measurements taken. Two minute (cp2m) fixed p readings were taken (total of 15 readings) using a 100 cm detector. The maximum result was <171 dpmM00cm (MOA). - a a 3. The numbers cincled are amroximate locations of wipes taken. Wipe results, Marianum p is 24 dpmM00cm2 & Maximumais 90 dpm/100an, a 4. All metal surfaces.

U o S$ N-Figure 13 : South Trench " Fill Soil' and Trench Sand / Debris Collection Locations f _h i' l I1 i 2 f 3 14 i5 67,8 9 !10! 11!12 13 14 I15 {16 i 17i18 i19 20 [ 21 l 22 23 ; 24 I 25 } 26 '27 :28 l29 l30131 32 133 134 ;35 36 37 36;39 !40 [ e + 4 y i t -., i.,. i p..p. a._ _.4_.._+..- L y..+ q. 4.. p.4_. 4,.;...a _.. ) 4. 4 4 _.4_ y.. j p n.p t._ pp,_ p ;._.; _..a_ p q _.p p. _ L. 1 i s i i. i g 1 i i i 6 .. j _ _ #. g.. ._. 4._L._1..i._b .._.. _i J ! .J. 2 _ !.d d _.i _.. ._ M. J k, 4lp Ly_j_LpJ._j _ L _ L I j 'i, !. l A -..3.-. y: j. i ! ._.p.. w y y 4 y. _ _... u f g...i -! i t ! i _p.,. g._. 1.-} _. _. 4 a.. ) ;._ i. 't .. _ 4 _ L _2.... _a. __. y p _% % 2 _& _t _4.. t i t B ..p. %j l; ; ; : i j j j ; i ; .!. p. 4 +j i ; i i j ; 1 }

i i ' l j

j ; + 9_ _ r+_ w_u p_ _ ; _4_ L,, a__ p_+_ _ e p._%j. 4 t-4.._ +._j_ r +_ _ _ 7' my t i i i r 4 t I i a i l 1 - i C i i i i ; ) i 1 i e D, p - y; .--.t.

I F '

e_.4_., g.. 7. g .. - _ [ z g ___. _ _ - g StoewALK .._.-g.___.g-. ~.g m _l_...g _l l l l:.. l Ig+_4 - j _g ) j; !.. ; 4 j 1 j ] 4.1, t_ _j .._.9 ._ F i } l t i. 2 . i ! > _.G__ _L . 4_ J _ ;_...d_.4. j d'.

4. __ L._...

..i.._ L. L.. j.. j-i t 5 ' i ; 1 ~. 4 _.g_ 4... ['. _. j Q 4_ ;.._p.. p 1-._ . 4 ___ p.

m l

1 : 1 i = 8 ' ;. _1.. i . L _ j.. _.;_. ! ' i ! ! i ; i ' : ! : ; i ^ : ; i ! 1 1 i ! ' i 1._._ i i. ! ! t

i 1 i

r i _. i._.2._ J.__ t. J _. p..L; _ L_ _ L_, 4J __4 _ _ J.

4.. L_._ a-._. !, 4,

..-._H !. t _%-... L l ; t 1

_ L_ t a.-.._ p.

_L._.p_4 a - - 4._t_ 4._ ! _ t..._}__l_ 1 _.L,.. a. I p[~t__ -4 ._. 4_ 4_ i -.2._ 4._ l t i I I ! l l !. ! i i i i i i I i Meced Area i { j , g q'

4._4__. g+ _.p.g

e. y.y._L' 4 _p p._

g4 _p _L_ e ..q._. t 7.. j._ . L. b_ g. .p. g p 1 _.y. p y. J _32% i e so. e mench ! ,~ +! l si-ne g' -+ +.. i ! i 1 i i i i s. _[_: y i 7,5.

y_4, q

y-- i 7 cI _.K i i } ] m' i ' r ! ' 1 = '. L 1 -ngg _5g h=.g.m a g

4. l._

_.-_.?_..p 4 - .a s ( ..M-. _... I i ; f ! i

1

_p. L. [.4 1._ {. _ %l 4._ }..._ _ pl_ _4 _..... 4.. .j_._d.. j _L_j _JM _. _.2 h,WPe*]4 N I. i,-. 4 i 1' q.. u.a 1. + y... 4...., _p %.,i l i l i I 1 4 i j t e .._.3 ,..g...A e t

; ; ! !, j j j j j

_.. 4. ... [ r + - u m.._+._ .N i ' l , 1 - ; j ... _. g!.. . ' _. 4 a _ 4_ 3 4 __, _ a q _ j 2_ m w._, _ .,4 y j i

i j 4._ !

i t

l l_

1 i i .4.., .y_ ._p __q_._ _...O unaccedAres

i i

! l ' i 1 i

i 4_

4 _.,.-. c _ _.., q

4. -.. 4 4 _. ; ;_

, p. ;..... L, q. _._;. _ p. .. _ ; _. 4 4 ! 4-..p AL. ; _ .2..._.'~ ...2 _p y .1. _. $.. d. 4... i.,.L,.. i U _ ' _ j i i t i

i i

- t. 3 i 1 o

i l ' ! !

i l.. .... i. 4 [.}. ]._.. j __ h.. [ _ d . 3. i.. I. 4 2 i l i 1 _1._ i l__ i .s...,-.j A !z_L 4.,_.u....1--;- -,..._.f.......,, b.._. ,,h

i !
..m1_

. __ 4.- y.

j.

___ :_ g.L,_ ! _, _. g _4 4._,j_ m z._. % 4x 4 _ _ f d g ;_ j ! i

.._. ~ g

,.g i stoew4uc i i _+._s g &# + g u_ _7. g 2 r .T 1 i .1.. - i -,. . 4 L 4 a _,.._ i i I . 4.bJ

La !

...U a i maa_ 4.. 4 = i

i..,. _, _.4_

U_...i _.' r t i i " l' 's 2 i 4 . t,. .f 4-J. I ..V 1 q. 1 4 .. p. i i - I .. -.w-,' -'. _;!. ;. 1 . i... L 1 i i l ! 2 .i .M j.. L. l .7 i 1.. L., f.. .L_.. .}..J._ _ i .._.4 I_... t 4 < i ! l _ j j i; . a _. L 2 _4 i X .,.4 +,..._. 4_._....#_ 2_

u. _ a, _

! ' i 4 J. _a F .4 m l i Notes: The numbers octagon on the South side (fit soi!) and trench (sand / debris) are approximate locations samples were diected. 2

P S N' Figure 16: Soil Sample Collechon LocCtionS {. j1 i 2 l 3 ;+ 4, i i 3 - > i i 14 l15 l16 ( 17:18 l19 : 20 j 21 l 22; 23 ! 24 j 25' 26 :27 :28 :29 '30 :31 [32.33 ;34 i = 1 1 4 5 _ L-.4 %... L _el 5 l 6 { 7 { 8 ; 9 ; 10 ; 11 ;12 !13 35 36 37 i36 39 140 ! I t A..._, .. f _.._p . _..;. _,. _ p.a 4

Q y,a _ 4.J.4.

4; A._L .L_ L ; _ 4_ i ~ . y <._ -. l

i j i: ; -

i 5 i ! ! q j i ) i i i j Mj;, 4_ ! _ L.41_ j _ i j, 4 d. _..[ _ }i.-. jd A._4.y 4 _.J l. ;. _j d. _[. _.. _b 4_.4_ L _.,4_j_ _ _.__ q 4 4,. L...j _ j,.._L L _.[__.4 a A I : i i i ! ! ! i i ! t ! t i

! ) i

! ! l t i l 1 i i i __I... h k.,.,..,.._ l._ ; _.4.m;.._,.j 4 _l. _.1_..% 1..J _. !._._ j._. 4.. l_ 4.. y _ + j __ % _l' 4_ _4 __ J._.,. 1._ j.. [.. 4._._L. [ _J _ j _.4._ _... ' _,. _ 4 B ! i ! i i l, ! : i ; j i 4... 4.._4_.4 %. p. j._.4. lr ! i i ; i ! ! I i i Trench kmed aber rummal - [ I i l l 1 l _ J.A.4._.n:!... - i ' ' i ' i t

i

'_ u _.2.a._._4_ j _.a 1 4.. 44.. - / d Red weste drem he -~ L m4-+ !-+ ! "-H-C..,i _. j j ~ i i /t . !. '2 y,_ p [ ;, p_., . g -, _.,_f_l. g _,_,_g7 g g4_, g +-,_,'_, y - 4 _,q ]._._j t 1 ' i i }4 g g _, g,_7_,j. {

y. Y D ' !

!,} p _.; i

j j j-stoEwALK j j -

.I c

L !

l-j._ i j i __._.+.4,_ _.+ a._.e 4_. 4q gg 3 _p 4-7 _j.. _.._.d _.j i

i S19

!.j _ i ss s

g..-,i +sy.

{j j l . _. - + _ ~.. : j { s4; j

j i se i s7!.'

F "f"? ! 4 _ - n n + +, sis!. 1 ! + -_n._. -.,a- _nn-_+ n gu 4_- .,._.. _!._ _ 4_.._ 4 s,ia3.~.yl u a _, _9 _lisir 4: ! i vl v!- G. j .. ss 4_ _.,j_ ; !L. p: ,. _ q.. . LJ _4._ A. ...a._ t__ .._._.4 l l _i ~ _+_ 44_ H ! i i ' 4_pjl__.p. ! q!.-.y g _4__ ss. _ + 4. q! ; ! 4.sisi.p_ %._[_a _,j_ _w aq_ i si4: i ! __ g p q q. p _. ,,.g. g . _a_ l !:,_i.i.#. i _g ,3,.3,3 r _.,1 _ii I I I ! I l t - gFrm ar-ww .,i i i 7 -4_I _+_ j., -.. r_,. . -q, l_ .s3 J sia ! - > i = i t ! i t t e 4 i i ..u L .. l_. 4 _y_{_. .. [._ + i 4 '.4.... y_._ EEMEWM a hls'E&h L%d.Wh&Them "535htihf ' 't Xmwh

arem, w

AEhe %-_r j j i .u_ a. w _( i l 1 i i i ! Q...-- 4. 4_. e.1... J. A.; _1 J_ J._ % i _ _ _; - .. 4__ u! _ !._ _._4 .q _.y --L ! i + l } j . L, i M. l i.! : t j 2..j_i.. Lg g, +. q_ q..# _._y.~._.J _p y _y 7,_ o m. a., ' _. 4 - ' p. -. c N 1' .. _, '..,i.. - 4 ,i 4,_ _i-s2s s'2s s24. !' - f i d _._., _+._ i ; .9._ L'._ p.' i _ r. 4 _. 4. .g._ .I I* 4 i l!

i..

m O i l l i i i i l s2o i u nnec* p e ! i i sz7 .! l .q j.. . _ y _... 4. 4 -.e S23._ _' y. _, _ g- - _,a 4 .p _, m._._ ,.+ .g,._.L._..L .4 y ~ 4.. . [ - p 4 __4 P i

i !

s2i t..j_ .'t. _ 4 l -r.a_ ___,.4 .,.1 -. t j-l i s2s i._ L +;._ g _ 4% % ;I. _.4_4 - 4 ..;_ y 3 4 ,..,w .+ ~ _.. _., _, _.. Q i I l i ! t i 3 $29 l l i- $22 4 l . i 4 -$l l 1 _._l _ 1 ' ~{.._.['. 4 h j-i R 5 i i i t i i 1 j l > > i i i i t - t "p._2 . { --jI"j ! _._1' _.,j . b'. {t i ..d q {i#__L_M, H._ J j 4 j._ ! _L l L [ ._ J -. b L]I_._. 4_ [

; {

1

l. _

l s t i i i I e l- ~i.d-I 4-- *j !. [ sioewAtxc i i 2 - - L~!-- +-I 2 l ..-_-l +- i L d-I t~- A---

I 94

+- I e-~ I C+ " - I * ' m -"+- & I - r. l T

i 4

~ - - - f -- - k -- 4 -- - ' A ? - E h '-d - '-t ' + r- ~I- -? i i 1 O =g.-...!.-. 4 +i j.... 4._ 4 ~ _,_b i 1 d U_., 4 mmm - com"osne sample kom bottom of me arench ;,. _, ' -r i I t sMace a subsurface samme : p i i ~ ; _,. 4, _ .q. _. g _ a. a ._4 m __a. 1 4 4 4 g.., i e t ) a i f i i i J -.a y f .__._.u t a L O = Grab sample f . n. L. _j, _ tN00009 - Compos #e sampde from side of me french __ L. d. .L .i.2 W ...i ; .4 i 1 , i I i.,. ! i : : l ; i 4 7 .p. y 4 9-4_ i = R, emovat of concrefe f-f ibof nMe) !, , - - + 1^ l ~

H~~

r Notes: 1. Total of 35 samples were collected in specific areas. See Table 6 for sample results. 2. All Soil,sandMebris surfaces. f - - _ _.. _ _ _. _ _... - -. -. - _ _ _ _. - - _ -.. _ _ _. _ _ _. _ _ _ _ _. _ _ _ _ _ _ _, _ _ _ _ _ _ _ _ _ _ _ _.. _ _, _ _ _ _ _, _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _______j

O v Figure 17 : Trench. Fixed Measurements b, s t e t i ;, ,,.,,. : i i ;. 4 ! I :(1 i 2 ;3 l4 S'i6 3 _ _ q -. 4_ w+.._u. 4 ~ q _ l - _. &7 l 8 } 9 410 j 11(12 j13 :14 l15 l16 i 17i18 l19 !20 l 21i 22l 23 j 24 ! 25; 26l27 i28 ]29 l30.31 :32 !33 ;34 l35 36 ;37 l 38:39 ' v. g q. e 4. _y... ; q. r ..g. p 4,. 4 __ 4 - q 4 4,..; i r i t i t 4, gm i i i 1 - i.., i + r 4 3 1 t i i. j-.,..-t-., ._a---,+,.- ._p-_4.. .1-d-..--. ~l.. .- -4.. 4 _4_.4-t+.-g-,-4 ..+!--4.._1..--f-.--v4_ +,...,i _.}. .4.. .y... .l-.i .i .ed~.4.- 4.' i t *

E

- + - - 4 .y i - i A'_.. % q__r..4, i i i t 4; J.... % _ A... . i i : ; 1 - ! ,' ( t i ! l, ' - _ 4.. q,.. .~..A .t_.4 _+_A.[.. . L.._t- ..w.. t.. e, A 4.._ - i

i l !

,, i < l i i i ! i l t _+,a_+_.... ,, -- f.. i, i, t _.4_ 4.. B...

l i ' ' ' i i

i i ' 1 i > ;

i. ; ;

.. 7 f i i ; i i i ! i i .,.-I

i

~ t ' ' u 4 -+ e -~n + ~ ' --n a,4.-.] -..v, .-.-4 i i i i, , a _.m - -. L L.-y. w +1 r i i.... _ -.4.n._ r i 1 _.._v. i- --.w.~...,. , ~ _ +. _ + _ C i i i i i ' t i i i i 4 _ _ _ i..,. _4 j... ! y, +. , m. _.'-~ TIT ~ i g_ 't~i I'T-i ~ T I# SIDEWALK'~~! q._ f' __.. " A I-'!

I'r

~ T ~* I E-- ~ ~P~F II'". ~i 7- "I t 1 I I . _ q.4 p_.pl.c_{.4 i D ) i i r ;

i !

i ; i i ! I 1 t i i 1

t_p g_;_.+, _4_.p.

p..g + E . i, a. 4 1. : 4,. 9 i 4 4 __- y _ g_.3 i o i , t 4 4 i ; , e 4 .J ...u. L _1 _.t._ A l i i ! 1 F 4 i f l 4.Qu -4. 1! q d1 1 i : l y_ :._.._.. L.m +.; _ L... - b _l

i !. >

1 p4

d. _-;.

L..._ t -a;. m --- - i

r. _ l p.

i 4 _.v 4 I l _ -. + _ a 4' _ +.. i a -l._ ! l l-l G j ; i j i i j .'m.- ) .,.-...+#_..L.. e, 3,

4. _ 4

~ -. _ _ r 4 _a j ~ __,_o l ; _. a.+. H

t ;

!vj.,!.,_,! l i

., teure,i j i !

,!. 4._._i _i__,; m hec 1 %_ l

i !

l i m.4_ 4 i i _ r__i ' i ! i m '. } ) ! i i ! ~; i ! i i i 1 o J._. _ L_

q.

L44.. L J d _ u. 4_.4._4..f. p. - _w. -- + _. 4 a _ _ p _ t, i.. T j _...i ..e.L.2.- 4 u .+ a L t

i
. > > - i ;: i !

i = : >. ; e t i 1 -f., 0 O yf -- ~- 4 g g gg gyg]pggg yg j 4A ~_4 4 h _.1 l la 1_4. _L. u _L_j _i, ~. .L1 p *~

4L

_._4 i ! l i pm P ! ' M l ! i - i . ; i li L+.__ ..L e..a 2 ~1 p:4 . _p_ ; b .. ;i. 4 ~_ _. _ +. +,. .p ! H.4' .-.p-a_ N ! t i l ! ! !. i. _ A-a i i m _ n.[ 1. _u y y _. mam_ r < _.u _ a_- .-r-4 -,a- __ 3 ~~ O i i _ %ml i 6 ! ! ! j i I j .. unarected Area > i . #a. _ 4 -2.... ; q._ , -_.p.+_e-.,.__._++_a__... A +. n. 4 _L l - - 4 ._...,a_ -__1_ +.2... % P t ! i j l ;

i i l i

i 4 -n e . L. 4-' 4- + - - - _ _ - 4 42 - - q : -,._ l. _w q.. _ _.a ( l 1 l '-~ l { l ' l i Q i _. _.4 g_ u w.u,_ ._-q R i i 1 4 - L p___1._ i L_, D _ L._.;- L . i i i i i i : i i i i 4 - I i -: ! 1 ---,J t -.-4-_; - L-a t 1 + s A.-+i _ i__.+ i _L _j. - j..-4._ L. L .1-t u _ S._ ~ l ! ; ~! ! 1 i i ! !. l SIDEwALKi i !

l. ' ! i !

i i ! d l-b II 4-L-~IIMl-j- IL 4~ d 11 ' J-- 1" ' I- . i i I t-I-M i 'Il-I-- Ld IM "I9 n T l ; l t 4 4 4 _j_ J 1 4 _. + o. - p..- 4 4 _ 4.. 1.

, 4-6 h..

-4 4.. _U j l. .~. -.-m l ! l i t 4 ... +., - + - 4. ~. ~g_..- .. + - t V 4 - __ i i. - 4. - 4 .4 -4._u 17 _.. _N __m L 4_ ,., i + t t-4 4 f +. _ L -.- h'. - 4 _, 4 u 4 ) 3 .p..-,. - 5 .g p - 4 4 c .= a + X im Scale Notes: a ard S. Scan results a anged from O cpm to 49 cpm and p ranged frorn 400 cpm to 600 com. 1. -100% insade the trendt (sides and bottom) was scanned for r 2. The values prowded are the approximate locations of measurements taken. Two minute (cp2m) fixed p readings were taken (total of 33 readings) using a 100 cm2 detector. The maximem results was 529 dpm/100cm2 3. As concrete surfaces. m ~

W Figure 18: Trench. Removable Contamination Results S N E-J 16 17 !18 19 [ 20 21 ' 22 l 23 ! 24 I 25 { 26 27 28 29 ;30.31 32 33 34 135.36 37 ; 38!39 40 i 1 2:3!4 j5 6l7 i8 C: 10,11 12 '13 !14 15 ~ -4 q_. _2 4, .u. l ,i s c g -+ L i + r r. t,, y 4 n. .1_ a i_;- 4._:__._,_, 2- ..._.7. _ _ x,.. _ 7 z ; _,__, _ x. _ _ _ r,, D s

I i i !

' SIDEWALKi.,_ z r_.,' i t . r =~_,__, 2 r _.r -r z r r-+ r-I q_ ;_ 4._.L..J _4 ._4. L'. ! . ; -; _ a_ 4_ .s_ gy ___L._ _p. _ +!. #_ .J.-. a 4_ 4 4. 4 _44 pg.. _._. _ L_.; i i t i E i i ' ' i ! ! ; i ; ! i ' i

! ! i - i j t ! i i j j v.g F..

t i i ! i 1.._, ._.4_ 4-G .a ._.1 1 _,4 i .q m. j ~ H . Anected Area ! l i __.4 i 3 _. s l . i , I 4 i ( ' I p.4_.. ..L 4 s 4 _ ~a_ g... ...r _.4 ..j i .i.. 4 i ...p. 2 [~~ f^ hidOku&$w h5550$YO?bbSW $$?SD$f&h5 Fj a g j ; w _ : R$ kSB '~ u_.

1. _

a_, e7 .e, s,,. a__ N m -c. i i i j. i ' O Unanected Area ' l l l ___4 ..n. I p 4.. - +- 1 _m 4 i

u. L.

1. _

i.. __ ; _..f.. Q .. L _4 l l R

t i '

..4... ... J [ t ! I j 1 4 .._.g __4 -. 4~ ..i... ..y._.i _ _ t

r_.
i i i

j StoEwALK! -. _.L..d .._4_...{._.% _.4_. a l_.u...__4-_.I_ 4--i J + S

I - - "j-4 9I-

-- --' " I 4 - - " I + -

! t j ; ! ' 1 j i i ! l l i. I " --- i - * + ", Ii --"-+-I'-- 2 -- *-- I i -+ -4 -I* I-T -4 4> d -... _. i U 4 i 4 V i I -- e i ~ 5 + 1.. tm Scans Notes: 1. The numbers circled are approximate locations of wipes taken. Wipe results, p is <10 dpm/100cm & a is <10 dpm/100cm, l r a 2. All metal concrete surfaces. I

APPENDIX A To l GA's Final Radiological Survey Report for Building 27 (EA-1) l I I " Process Knowledge Report for the EA-1 (Bldg. 27) l Laboratories" dated June,1997 I I I [ M

i hCBnEEERLJETtmnCE m,m m. m PROJECT CONTROL ISSUE

SUMMARY

DOC. CODE PROJECT DOCUMENT NO. REV. RGN 9009 PC-000485 0 TITLE: Process Knowledge Report for the EAl (Bldg. 27) Laboratories APPROVAL (S) REVISION CM APPROVAU PREPARED RESOURCE / DESCRIPTION / DATE REV BY SUPPORT PROJECT W. O. NO. C-Il-97 HMN lSyyg g } f) .%s>$3^'MMk ~ 0 . Hill ~ J. Greenwood G. ramblett InitialIssue (*- 81-f 7 W. O. 09009.304.10000 fJUN 121997 .fW([f f s j V. Nicolaye l l l @ONTINUE ON GA FORM 2175-1 o See List of Effective Pages O GA PROPRIETARYINFORMATION THIS DOCUMENT IS THE PROPERTY OF GENERAL ATOMICS. ANY TRANSMITTAL OF THIS DOCUMENT OUTSIDE GA WILL BE IN CONFIDENCE. EXCEPT WITH THE WRITTEN CONSENT OF GA, (1) THIS DOCUMENT MAY NOT BE COPIED IN WHOLE OR IN PART AND WILL BE RETURNED UPON l'.EQUEST OR WHEN NO LONGER NEEDED BY RECIPIENT AND (2)INFORMATION CONTAINED HEREIN MAY NOT BE COMMUNICATED TO OTHERS AND MAY BE USED BY RECIPIENT ONLY FOR THE PURPOSE FOR WHICH IT WAS TRANSMITTED. M NO GA PROPRIETARY INFORMATION lPAGE j OF

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 I l UST OF EFFECTIVE PAGES Page Number Page Count Revision i through lii 3 0 1-1 1 0 2-1 1 0 3-1 through 3-17 17 0 l 4-1 through 4-2 2 0 51 through 5-2 2 0 Total 26 i I I I I I I I g I

a PROCESS KNOWLEDGE REPORT FOR THE EA1'(BLDG. 27) LABORATORIES PC-000485/0 TABLE OF CONTENTS Eage,No_. a i: l 1.0 . PURPOSE 11 l l l-2.0. SCOPE 2-1 3.0 REPORT 3-1 l 3.1 BUILDING HISTORY 3-1 3.1.1 -1964 to -1974 3-1 3.1.2 ~1974 to -1986 3-2 3.1.3 -1986 to -1996 3-2 3.1.4 ~1996 to -1997 3-2 l 3.2 HISTORY OF EACH CURRENT ROOM IN THE BUILDING 3-2 l~ 3.2.1 Mechanical Room 3-2 3.2.2 Rm. 27/100, Conference Room 3-3 ) l 3.2.3 Rm. 27/101 Gamma Spectrometry Laboratory 3-3 l j' 3.2.4 Rm. 27/101 A Physical Testing Laboratory 3-4 3.2.5 Rm. 27/1018 Office 3-5 3.2.6 Rm. 27/102 Offico 3-6 3.2.7 Rms. 27/103 & 27/104 Offices 3-6 1 3.2.8 Rm. 27/105A Chemical Storage 3-6 3.2.9 Rm. 27/105B Laboratory Supply Storage 3-7 3.2.10 Rm. 27/106 Emission Spectrometry Laboratory 37 q -3.2.11 Rm. 27/107 Gas Laboratory 3-8 3.2.12 Rm. 27/108 Radiochemistry Laboratory 3-8 3.2.13 Rm. 27/109 Radiochemistry Laboratory 3-9 3.2.1< Cim. 27/110 ICP Laboratory 3 10 3.2

Pm. 27/"i Liquid Chromatography Laboratory 3-11 l

3.2.16 Rm. 27/112 Combustion Laboratory 3-12 L 3.2.17 Rm. 27/113 Sample Preparation Laboratory 3-13 l 3.2.18 Rm. 27/114 lCF Laboratory 3-14 1 3.2.19 Rm. 27/115 Mass Spectrometry Laboratory 3 15 3.2.20 Rm. 27/116 Environmental Laboratory 3-15 3.3 CURRENT STATUS AND CONDITION OF THE BUILDING 3-16 3.3.1 Existing Radiological and Hazardous Material Contamination 3-16 g L '3.3.2 Physical Condition of the EA1 (Bldg. 27) Structure 3-17 4.0 FIGURES 41 41: EA1 (BLDG. 27) AND ADJACENT AREAS 41 4.2: EA1 (BLDG. 27) PLAN VIEW DETAll 4-2 l._

5.0 REFERENCES

51 l: 5.1 PERSONNEL REFERENCES 5-1 5.2 GA FACILITIES ENGINEERING DRAWINGS 52 i lii I m

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 1.0 PURPOSE The purpose of this report is to provide an information basis for the planned efforts toward the decontamination and decommissioning of the EA1 laboratory building, GA Bldg. 27, and the j adjacent yard areas. The overall intent of the report is to identify the type, quantity, condition, and location of radioactive and hazardous materials which are, or may be, present as residual contamination in the subject area. i i Laboratory work in EA1 (Bldg. 27) is controlled and monitored under a Radiological Work Authorization, reviewed, approved, and issued by the GA Licensing, Safety, & Nuclear Compliance (LS&NC) organization. As described in that document, the possession and use of Special Nuclear Materials (SNM) in the subject area, is authorized and controlled by the GA l Nuclear Materials Accountability (NMA) organization, under Material Balance Area #R-1. I { l 1' 11 I l

l PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 l 2.0 SCOPE j The scope of this report covers the laboratory and office space housed in EA1 (Bldg. 27) and pertinent adjacent yard areas, (refer to Figures 4.1 & 4.2). Historical records and process knowledge information utilized in the preparation of the report cover the entire operational time period for the subject building from the original construction to the present. Most of this data was gathered from interviews with certain cognizant individuals who worked in or managed the facility, including the current facility Principal investigator and the GA Health Physics surveyor currently assigned to the building. Section 5.1 identifies the personnel utilized as information sources for this report. j i I l I ( 2-1 1 l l

_=._ _ _. _. _.-______. _ _ __ _ _ _ _ _ PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG,27) LABORATORIES PC-000485/0 3.0 REPORT 3.1 BUILDING HISTORY 3.1.1 -1964 to -1974 Construction of EA1 (Bldg. 27) was carried out between 15 Sept 64 and 7 Apr 65, on a site adjacent to, and immediately west of, the TRIGA* Reactor Facility (Bldg. 21), (see Figures 4.1 & 4.2). The buiiding is of concrete masonry construction, with exterior dimensions of 41.3 ft x 112.0 ft (12.6 m x 34.1 m), which houses an interior space of approximately 4400 ft (409 m'). EA1 (Bldg.

27) was designed as a rectangular open shell with no internal load bearing walls; this feature allows forit.e versatile configuration of, and the simple modification of, the housed laboratory and office spaces. The only permanent interior concrete block walls enclose the small Mechanical Service Room, located near the center of the building east wall.

The building concrete deck incorporates a sub-floor Service Trench, -2 ft wide i x ~3 ft deep (~0.61 m x -0.91 in), situated along the entire north-south central axis of the building. The Service Trench accomodates installed service plumbing including, supply lines for domestic water, deionized water, natural gas, and compressed air, and separate drainage lines routed to the sanitary sewer system and the Radioactive Liquid Waste Holding Tank, located northeast of the adjacent EA1-Bunker, Bldg. 27-1. The central sub-floor i Service Trench features thirteen -3.5 ft wide x ~4.5 ft long (~1.1 m x -1.4 m) east-west branches, to accomodate service plumbing for the individual laboratories in the building, and a main branching trench, -3.5 ft wide x ~13.0 ft long (-1.1 m x -4.0 m), routed under the Mechanical Room. The central Service Trench is crossed by one radioactive drain line, (routed from Rm. 27/109 to Rm. 27/108), in addition, the radioactive drain line serving the sink in Rm. 27/116 is routed through the central Service Trench, from the northem trench terminus to Rm. 27/108. The radioactive drain lines serving the EA1 (Bldg. 27) laboratories are expected to intemally contain residual radioactive contamination. The sub-floor Service Trench has been reportedly flooded a t number of times, due to leakage or failure of clean (domestic) water supply lines serving the building. Also reported (in 1989) was a single incidence of flooding into the Service Trtench during the modification of the radioactive drain system, which involved the installation of the aforementioned branching line l serving the sink in Rm. 27/116. The water leaked during that incident reportedly issued only from the newly installed branch line, and was presumably clean; no contamination was discovered during follow-up surveys in the affected portions of the Service Trench. Incidental flood water has reportedly seeped out of the Service Trench within a few days, indicating that . the Service Trench may not be fully isolated from the surrouriding soil. Materials and soils, situated beneath or near the installed facility radioactive drain piping, may contain residual rafoactive contamination, as a result of leakage from the system. Based on available process knowledge, no i radioactive materials have been introduced into the sanitary sewer drain lines [ serving the building. l 3-1

= PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 The GA Neutron Activation organization occupied the building immediately after construction was completed. This group established offices in the south end and northeast comer, and set up radiochemistry laboratories in the rest of the building. The laboratories were used primarily to prepare target samples for neutron irradiation and to perform post-irradiation radiochemical separations; a number of other radiochemical experiments were also carried out in these laboratories. Section 3.2 of this report will deal with the use of each room in the building as it is currently configured (see Figure 4.2); it should be noted that there have been several room modifications made over the years. The GA Neutron Activation organization was sold to IRT Corporation in 1973; IRT Corporation thereafter vacated Bldg. 27, and relocated operations off-site. 3.1.2 ~1974 to ~1986 The building floor plan was significantly altered in 1974 and then occupied by several groups during this period. The alterations will be discussed separately for each area in section 3.2. The Radiochemistry end Gamma Ray Spectrometry Groups were using the labs and offices in the middle and southem end of the building for fuel bumup analysis, neutron activation analysis, radiochemical analysis, and gamma ray spectrum analysis. HTGR and GCFR fuel development groups were using the labs and offices at the northem end of the building for fuel studies and quality control analysis. 3.1.3 ~1986 to ~1996 The GA Analytical Chemistry and Radiochemistry groups were combined into the GA Chemistry group, which then occupied the whole building except the laboratory in the northwest comer (Rm. 27/114) and the Conference Room (Rm. 27/100) in the southeast comer. Rm. 27/114 was occupied by several different groups during this period; Rm. 27/100 Conference Room was assigned to the TRIGA* Reactor Facility (TRF) organization. 3.1.4 ~1996 to ~1997 Operation of the GA Chemistry organization was terminated in 1996, and administrative control of EA1 (Bldg. 27) was assigned to the GA Decontamination and Decommissioning (D&D) organization. Current authorized work in the building is limited to the survey, processing and removal from the area of all laboratory equipment and supplies, and performance of certain analytical measurements in support of the D&D group, (i.e., gross alpha / beta counting and gamma spectral analysis of samples). 32 HISTORY OF EACH CURRENT ROOM IN THE BUILDING 3.2.1 Mechanical Room i j 3.2.1.1 ~1965 to ~1997 The use of this room has remained constant throughout the life 3-2

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 i of the building. It contains the blowers and pumps that provide heating, air conditioning, and ventilation for the building, it also contains the Hot Water Heater. This is the only permanent room in the building with concrete block walls. The retum air vent from the laboratovy hallway to this room was sealed off -1993 to reduce the pressure difference between the inside and outside of the building. ~ Since no laboratory activity was ever carried out in this room, no contamination is expected. However, a survey should be performed to insure that no contamination was introduced from the vent in the hallway. 3.2.2 Rm. 27/100 (Conference Room) 3.2.2.1 -1965 to ~1974 This area served as a meeting room with no laboratory activity. 3.2.2.2 -1974 to ~1964 f.. The eastem half of this room was converted to an Electronics Shop for repairing nuclear assay equipment. Small sealed sources were kept in the shop to test and calibrate this equipment. No residual contamination is expected to be present in this area due to these operations. The westem half was used as office space by the gamma spectrometry group. 3.2.2.3 -1984 to -1997 This area was converted back into a Conference Room under ( the control of the TRIGA* Reactor Facility organization. No laboratory activity occurred during this time. ( This room is currently used as a staging area for material that i has been cleared as not radiologically contaminated prior to disposition. No radiological or hazardous material contamin-ation is expected in this area. 3.2.3. Rm. 27/101 (Gamma Spectrometry Laboratory) 3.2.3.1 -1965 to ~1974 This area was used as office space. No laboratory activity occurred during this time. 3.2.3.2 ~1974 to -1986 This area was used as part of the Gamma. Ray Spectrometry 3-3 r

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 laboratory. There were three Germanium Detectors shielded by large caves made from clean lead bricks. These were connected to various computers for data acquisition and analysis. All radioactive sources were sealed and wipe checked for extemal activity before they were allowed in the laboratory. The area was accidentally contaminated a few times by broken containers, but all spills were immediately cleaned to background levels to prevent contamination of the detectors. 3.2.3.3 -1986 to -1997 This area was converted into a combined Radiometric Labora-tory, equipped with Proportional Counters, Alpha Spectrometry Systems, and a Liquid Scintillation Counter, in addition to the Gamma-Ray Spectrometry System. Since samples submitted for alpha / beta counting c:r.not be analyzed if they are sealed, that laboratory restriction was relaxed. However, strict adherence to radioactive cleanliness was maintained, in order to prevent contamination of any of the equipment. This j equipment is still used for measuring the lowest levels of environmental contamination. A lead brick cave was built near the center of the south wall, to accomodate radioactive sources used for calibration of the Gamma-Ray Spectrometry System. Several spills of Mercury Porosimeter specimens and mercury have been reported, on the floor near the door to Rm. 27/101 A; such incidental spills were cleaned up immediately. The shielded storage cave is the only location where significant radioactive contamination is likely to be found. The lead in this room should be clean. Some of the equipment has been removed from this laboratory. The floor may have minor mercury contamination. 3.2.4 Rm. 27/101 A (Physical Testing Laboratory) L 3.2.4.1 ~1965 to -1974 i This area was used as office space. No laboratory activity occurred during this time. 3.2.4.2 ~1974 to -1984 This area was used as part of the Gamma-Ray Spectrometry Laboratory. (See Section 3.2.3.2) i 3.2.4.3 ~1984 to -1985 This area was converted back to office space. No laboratory l 3-4 t

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 activity occurred during this time. 3.2.4.4 ~1985 to -1986 This area was converted to a Radiation Counting Laboratory housing the Proportional Counters for performing gross alpha / beta analysis. No known contamination of this crea occurred during this time. 3.2.4.5 ~1986 to -1997 This area was converted to a Physical Testing Laboratory housing the Thermogravimetric Analyzer, the Mercury Porosimeter, the Viscometer, and several microscopes. It was also used as a storage area for a variety of equipment and procedure manuals and a staging area for gamma ray and liquid scintillation samples. There were several spills of mercury on the floor from the Mercury Porosimeter. These were cleaned up immediately. Most of the equipment has been removed from this laboratory. No known radioactive contamination of this area occurred. The floor may have minor mercury contamination. 3.2.5 Rm. 27/101B (Office) 3.2.5.1 -1965 to ~1974 This area was used as office space. No laboratory activity occurred during this time. 3.2.5.2 -1974 to -1985 This area was used as part of the gamma ray spectrometry laboratory. (See section 3.2.3.2) A lead brick cave was built in the northwest comer of this room, to accomodate both radio-active sources (for calibration of the Gamma-Ray Spectrometry System), and radioactive samples prior to analysis. The vicinity of the lead brick cave is the only location in this room where residual radicactive surface contamination is expected to be found. There is no known hazardous material contamination in this room. 3.2.5.3 ~1985 to -1997 This area was converted back to office space. No laboratory activity occurred during this time. 35 l

_. -.. _ _. _. ~. _. PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 3.2.6 Rm. 27/102 (Office) 3.2.6.1 ~1965 to -1974 There was no wall between what is now Rm. 27/106 and this room, so this area was part of that larger laboratory. See section 3.2.10.1 for usage during this time period. 3.2.6.2 ~1974 to -1997 This area was used as office space. No laboratory activity occurred during this time. The concrete deck under the vinyl - flooring is potentially contaminated, but this is not likely. '3.2.7 Rms. 27/103 and 27/104 (Offices) 3.2.7.1 ~1965 to -1997 This area was used as office space. No laboratory activity occurred at any time. 3.2.8 Rm. 27/105A (Chemical Storage) 3.2.8.1 ~1965 to -1974 There was no wall between Rm. 27/105A and Rm. 27/1058. l This whole space was used for storage of new office and laboratory supplies. There was also a clean refrigerator and storage area. No laboratory activity occurred in this area l during this time. l 3.2.8.2 ~1974 to -1975 This area was used as office space. No laboratory activity occurred in this area during this time. 3.2.8.3 -1975 to -1997 This area was used for dry chemical storage and a few laboratory supplies. No other laboratory activity occurred during this time. The shelves in this area may be contaminated with very small quantities of hazardous inorganic dry chemicals due to spills or breached containers. There was no known radioactive i contamination of this area. All of the chemicals and supplies have been removed from this room; however, the Mercury Porosimeter system is currently stored in this room. 3-6

1 PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 3.2.9 Rm. 27/1058 (Laboratory Supply Storage) 3.2.9.1 -1965 to -1997 This area was used as laboratory supply storage space. The telecommunications control center is also located in this room. No laboratory activity occurred in this area at any time. This room is nearly empty, and there is no known contamination in this room. 3.2.10 Rm. 27/106 (Emission Spectrometry Laboratory) 3.2.10.1 ~1965 to - 1974 This laboratory was used primarily for preparing samples for activation in the TRIGA* Reactor Facility, and processing irradiated samples for counting analysis. There were also several short term radiochemical experiments performed in this laboratory, some of which led to radioactive material spills which were immediately cleaned up. 3.2.10.2 ~1974 to ~1985 The southem part of the laboratory was walled off to create offices, and the remaining space used as a Radiation Counting lam,ratory. The room featured several lead caves for shielding Nal(TI) Gamma-Ray Detectors, and Proportional Counters for gross alpha / beta analysis. GA Health Physics personnel occu-pied part of area during the subject time period as office space. 3.2.10.3 ~1985 to ~1986 Unused. 3.2.10.4 ~1986 to -1997 The Emission Spectrograph and X-ray Fluorescence Analyzer were moved into this laboratory. Most of the chemical g standards for these systems were also moved to this area. The g area in and around the fumace of the emission spectograph is contaminated with uranium, thorium, and associated long-lived daughter nuclides, as a result of elemental analysis operations. l There is a locked cabinet under the Emission Spectrograph which is used to store the Special Nuclear Material (SNM) for the building, so this room had an intrusion alarm and a separate key for SNM control. The alarm has been removed because the SNM inventory has been reduced to less than 15 grams. A Deli Case Refrigerator and a Freezer were moved 3-7

l l PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 into the laboratory to accomodate samples requiring low temperature storage, as well as a radioactive Sample Storage Locker. The Fume Hood in this laboratory was used for various types of uranium analysis. There were organic chemicals stored under the hood in safety cans. Recently there have been several radioactive waste barrels with SNM stored in this laboratory as weil as a large radioactively contaminated Lead Transfer Cask. Most of the chemicals have been removed, but the equipment and samples are still there. There is probably either hazardous inorganic chemical or radioactive contamination in various parts of this room. 3.2.11 Rm. 27/107 (Gas Laboratory) 3.2.11.1 ~1965 to -1974 This room was used as a combination office and general Radiochemistry Laboratory. No known specific contamination incidents occurred. 3.2.11.2 ~1974 to -1997 This room was used primarily for storage of tools and hardware and for construction of small items for use in the other laboratories. The Fume Hood was used for work with radioactive Kr and Xe as well as a few other very low level activity experiments. Some general laboratory supplies were also stored here. In -1989, a Refrigerator and Microwave for lunch storage and preparation were located in the northwest comer of the room and a Copy Machine was located on the t north bench. Organic chemicals were stored in safety cans under the Fume Hood. The chemicals and most of the tools have been removed. There is possible radioactive contamination in the Fume Hood. The Fume Hood features a transite working surface, but the presence of additional hazardous materials is unlikely. 3.2.12 Rm. 27/108 (Radiochemistry Laboratory) l 3.2.12.1 ~1965 to ~1997 This room has always been a general Radiochemistry Laboratory. The sink in this laboral ry drains into the Radioactive Liquid Waste Holding Tank located north of the h EA1-Bunker (Bldg. 27-1); this tank and the drain lines were B added in 1974. This laboratory contained the Electronic Balance which was used for all types of weight measurements 3-8

i PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLOG. 27) LABORATORIES PC-000485/0 l l (i.e., organic, inorganic, radioactive, solutions, etc.). There were organic chemicals stored under the Fume Hood in steel l safety cans as well as liquid acid and base reagents. Some radioactively contaminated glassware was stored in the l cabinets and drawers after cleaning. Lower level radioactive standard solutions and samples were also stored in the l cabinets. The Fume Hood developed a leak in -1992 and was - l replaced with a new unit. This laboratory has been used for a wide variety of radiochemical experiments and has incurred - several spills, all of which were immediately cleaned up. The chemicals and balance have been removed from the laboratory. The Fume Hood is contaminated with radioactive material, and it is a probably contaminated with hazardous materials. There is possible contamination with radioactive and hazardous materials in most areas of the room. l l 3.2.13 Rm. 27/109 (Radiochemistry Laboratory) l 3.2.13.1 -1965 to -1997 This room has always been used as a general radiochemistry laboratory. The sink in this laboratory drains into the Radioactive Liquid Waste Holding Tank located north of the EA1 Bunker (Bldg. 27-1). There were organic chemicals stored L under the Fume Hood in steel safety cans as well as liquid acids and bases. Some radioactively contaminated glassware l was stored in the cabinets and drawers after cleaning. Lower l level radioactive standard solutions and samples were also stored in the cabinets. This laboratory has been used for a wide variety of radiochemical experiments and has incurred sessrel spills which were immediately cleaned up. In -1988, [ there was a leak in the plumbing under the sinis for several l days which contaminated the cupboard and floor under the l sink. There was a Glove Box which was removed a few years i ago on the benchtop above the cave. It was used for analysis j of transuranic materials during the late 1970s. There is a Lead Brick Storage Cave under the bench along the l southwestem wall which contains the high level radioactiv,ty l standards, stock solutions, and samples. This Storage Cave is highly contaminated with radioactivity on the inside and many or most of these lead bricks are radioactive!y contaminated. There are also several lead pigs used for shielding radioactive materials near this cave which are also contaminated with radioactivity. There is a Muffle Fumace in the northwest comer of the room which is contaminated with uranium and possibly other radioactive materials. The cabinet above the bench in the southeastem corner of the laboratory is used to store the non-3-9

[ { PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 (. SNM inventory of uranium and thorium for the facility. All ( nonradioactive chemicals have been removed from the laboratory. The hood is contaminated with radioactive material and is probably contaminated with hazardous materials. There is possible contamination with radioactive and hazardous materials in most areas of the room. 3.2.14 Rm. 27/110 (ICP Laboratory) 3.2.14.1 -1965 to -1974 This room was a general Radiochemistry Laboratory, it was reported that mercury was spilled on the floor a few times. 3.2.14.2 ~1974 to -1986 A perchloric acid Fume Scrubber Hood was installed in this laboratory to allow for the dissolution of irradiated fuel particles. Radiochemical analysis of irradiated fuel, for determination of fuel bumup, was the primary activity in this laboratory. This hood used water to scrub the effluent fumes from the dissolution and dumped contaminated water into the Radioactive Liquid Waste Holding Tank. There was a water tank for the Fume Scrubber Hood situated on a small concrete pad next to the lab on the west side of the building. This water tank overflowed several times when automatic check valves failed to function properly. The water in this tank was slightly radioactive, and radioactive contamination of the soil near this pad is possible. There was a sink on the east side of the Fume Scrubber Hood which was also hooked up to the Radioactive Liquid Waste Holding Tank. The Fume Scrubber Hood and the sink were removed in -1984 because the Fume Scrubber Hood began leaking radioactive contamination onto the floor. The pipes leading from the scrubber on the roof to the makeup tank ( were not removed. It was reported that Mercury was spilled on ( the floor in ~1964 during a rare earth separation test. This mercury was cleaned up immediately. 3.2.14.3 ~1986 to -1997 This lab was converted to Analytical Chemistry use and contained the Atomic Absorption (AA), infrared (IR), and Ultraviolet (UV) Spectrophotometers. A nonradioactive sink was installed in the northeast comer and the hot drains serving this room were sealed off. The cabinets along the south wall were used to store solid organic chemicals, and the cabinets along the north wall (removed in 1993) were used to store inorganic solution standards. Some of the samples analyzed in 3-10 l

l ( PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG 27) LABORATORIES PC-000485/0 f this laboratory contained low levels of radioactive nuclides. There was a refrigerator and freezer combination along the north wall next to the sink which contained organic standards which required low temperature storage. There were organic chemicals stored under the sink in steel safety cans. In 1994, an Inductively Coupled Plasma (ICP) Spectrophotometer was installed in this laboratory, and the IR and UV Spectrophoto-meters were relocated to Rm. 27/112. In the last few years, this laboratory was also used for high-pressure filtering and analysis of various waste samples. All of the equipment and materials have been removed from this room. The main areas of concem for current radioactive contamination are the concrete floor under the benches in the southem center of the room and in the ventilation ducts for the Fume Scrubber Hood. The cabinets on the south wall may be contaminated with residual hazardous materials, and the floor may be slightly contaminated with residual mercury. i 3.2.15 Rm. 27/111 (Liquid Chromatography Laboratory) 3.2.15.1 -1965 to -1974 This room was a general Radiochemistry Laboratory. The sink in this laboratory drained into the sanitary sewer. It was reported that mercury was spilled on the floor a few times, but it was immediately cleaned up. 3.2.15.2 ~1974 to -1984 This laboratory was occupied by the HTGR Fuel Development Group. The main activities involved fuel hydrolysis and graphite oxidation experiments on unirradiated fuel. 3.2.15.3 -1984 to -1986 An Alpha Spectrometer and a Liquid Scintillation Counter were set up and calibrated by the Radiochemistry Group in this laboratory. This equipment was moved to Rm. 27/101 in 1986. 3.2.15.4 -1986 to -1997 Gas and Uquid Chromatography Systems were set up in the 7 laboratory for Analytical Chemistry use. The lab was also used '~ for other general analytical chemistry tests. Some of the samples analyzed in this laboratory contained low levels of radioactive nuclides. Standard solutions for the Liquid 3-11 / lr t

. - -. - - -. ~ =. - PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 Chromatograph, chromatographic resins, and some other chemicais were stored in the cabinets on the south wall. There were organic chemicals stored under the hood in steel safety cans as well as liquid acids and bases. The ventilation duct from the Fume Hood in this laboratory developed a pinhole breach in 1996, resulting in radioactive contamination of the equipment and workbench in the northwest corner of the lab. All of the chemicals, most of the equipment, and some of the supplies have been removed from this laboratory. The Fume Hood probably contains radioactive contamination and may contain very small amounts of hazardous material. The cabinets on the south wall may contain very small amounts of hazardous material, and the floor may have minor mercury l contamination. 3.2.16 Rm. 27/112 (Combustion Laboratory) I 3.2.16.1 -1965 to -1974 The wall between what is now Rm. 27/112 and Rm. 27/114 did not exist. See Section 3.2.18.1 for a description of the use of this area. 3.2.16.2 ~1974 to ~1986 This laboratory was occupied by the HTGR Fuel Development Group. The main activities involved fuel hydrolysis and graphite oxidation experiments on unirradiated fuel. 3.2.16.3 -1986 to -1997 1 L The Combustion Analyzers for carbon, sulfur, and oxygen were l moved into this laboratory, and several Lindberg Fumaces were added for performing other high temperature analyses. Most of these analyses were performed on unirradiated fuel resulting in widespread low levels of radioactive contamination on the l benchtops and in the drawers. Contaminated fumace tubes l were also stored in many of the drawers leading to further l spread of this low level contamination. Chemicals directly related to the combustion analysis were stored in the wall cabinets. A new 6' Fume Hood was added along the north wall in -1995 and the northem part of the laboratory was used as a sample preparation area for volatile and semivolatile organic analyses of waste samples. This area was also used as a I-sample preparation area for analysis of waste samples. r 3-12 t

l l PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 l Most of the equipment and materials and the Fume Hood have been removed from this laboratory, it is currently being used as a staging area for checking items from the other laboratories for radioactive contamination. Some of the benchtops and drawers (south) contain radioactive contamination and (north) may contain very small amounts of hazardous organic material. The floor may be slightly contaminated with either radioactive or hazardous organic materials. j. 3.2.17 Rm. 27/113 (Sample Preparation Laboratory) 3.2.17.1 -1965 to -1974 This room was a general Radiochemistry Laboratory. The sink 3 in this laboratory drained into the sanitary sewer. There were no known incidents of contamination. l 3.2.17.2 -1974 to ~1986 This laboratory was occupied by the HTGR Fuel Development Group. The main activities involved quality assurance and quality control analyses of the fuel. These analyses consisted mostly of thorium hydrolysis and leach-burn / leach tests on unirradiated fuel. 3.2.17.3 -1986 to -1997 l L This laboratory was used as the primary sample preparation area for dissolving, separating, and diluting aliquots for use in the analytical instruments in the other laboratories. There were i also a few small instruments like pH Meters in this laboratory. Some of the samples analyzed in this laboratory contained low levels of radioactive nuclides. There were organic chemicals stored under the Fume Hood in steel safety cans as well as liquid acids and bases. There were organic chemicals stored under the sink in steel safety cans. There were inorganic liquid standards and pH buffer solutions stored on the benchtop and in the cabinets. All of the chemicals and some of the equipment and materials have been removed from this laboratory. The Fume Hood probably contains radioactive contamination and may contain very small amounts of hazardous material. The cabinets on the walls and the benchtops may contain very small amounts of L hazardous material. I G 3-13 f i

l i PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 3.2.18 Rm. 27/114 (ICF Laboratory) 32.18.1 -1965 to -1974 This area was used primarily as a Counting Laboratory for analyzing samples after neutron activation. There were several detectors in caves made with lead bricks along with associated electronics equipment. There was a partition separating the northem end of the room from the rest of the room and this area was used as an Electronics Shop for repairing all of the electronic equipment in the building. There were no known incidents of contamination. 3.2.18.2 ~1974 to ~1980 This laboratory was occupied by the GCFR Fuel Development Group. A sink was added along the westem wall which drained into the Radioactive Liquid Waste Holding Tank. A Fume Hood was added along the new southem wall which was built to separate this room from Rm. 27/112. This group performed fuel bumup analyses on irradiated fast reactor fuel which contained much larger concentrations of transuranic radioactivity than HTGR fuel. 32.18.3 ~1980 to ~1993 This laboratory was decontaminated and refurbished in 1980. The radioactive sink was removed, and the drain line capped. The area was then occupied by GA Facilities, and was used to decontaminate large items from various buildings at GA. There were no known incidents of contamination during this period. 3:2.18.4 -1993 to -1994 This laboratory was used to test the process of vitrifying contaminated waste to render it harmless using a High Temperature Fumace. There were no known incidents of contamination. 3.2.18.5 ~1994 to -1997 This laboratory was used by the inertial Confinement Fusion (ICF) Group to store equipment intended to be used for loading tritium into glass beads. No experimental work was performed during this period. i Most of the equipment and material have been removed from this lab, and it is currently being used as a staging area for radioactively contaminated equipment. The Fume Hood is 3-14 1 l l

i l PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 contaminated wih radioactive nuclides including transuranic nuclides, and the floor may be contaminated with radioactive material. There may be hazardous material in the Fume Hood and on the floor. 3.2.19 Rm. 27/115 (Mass Spectrometry Laboratory) 3.2.19.1 -1965 to -1986 This area was used as primarily as office space. An experimental Wave Chamber was set up in this room around 1970, but no radioactive or hazardous materials were used. 3.2.19.2 -1996 to -1987 The Gas ChromatographMass Spectrometer (GCMS) and another Mass Spectrometer were moved into this room. This old equipment was seldom used and was discarded when a newer GCMS was obtained in -1990. This machine was replaced again in 1993 with a new GCMS. Two other Gas Chromatographs and a small Benchtop Hood were added in -1993. These systems were used almost entirely to analyze gasses and only extremely small quantities of hazardous or radioactive material were ever brought into the area. All of the equipment and materials have been removed from this room and there is probably no radioactive or hazardous contamination here. 3.2.20 Rm. 27/116 (Environmental Laboratory) 3.2.20.1 -1965 to -1971 This area was used as office space. No laboratory activity occurred during this time. 3.2.20.2 -1971 to ~1974 Non-destructive uranium assay of unitradiated product fuel rods was performed in this room. The analytical equipment utilized for this purpose featured a passive neutron source and integral electronic counting instrumentation. No known contamination of the room occurred during this time. 3.2.20.3 -1974 to ~1988 ThM area was used as office space. No laboratory activity occurred during this time. 3-15

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 l 1 3.2.20.4 -1988 to -1989 This area was occuped by TRIGA Reactors Facility personnel, and used for processing, analysis and release of irradiated gemstones. No contamination of the area occurred during this i period. i 3.2.20.5 -1989 to -1997 A sink was added to the northwest comer of this room with the drain connected to the Radioactive Liquid Waste Holding Tank, and a Fume Hood was added along the west wall. This laboratory was used to prepare enviramce.M samples for j radiochemical analysis. Only low leC: or radioactivity were brought into this laboratory in order to avoid contaminating the lab and other samples. There was a fire in this laboratory in 1 1994 which destroyed the Fume Hood and the equipment and samples inside it. This fire also caused extensive smoke damage to the rest of the laboratory. The Fire Sprinkler j System was on for ~20 minutes which flooded the floor and caused water to drain out of the northeast outside door. No activity above natural background was found in this water. The damaged Fume Hood was replaced with a new Fume Hood and the laboratory was cleaned up for continued use. The hood and all of the aquipment and materials have been removed from this laboratory. The sink and its drain and the ducts from the hood may be radioactively contaminated, but there is probably no other radioactive or hazardous contamination in the room. 3.3 CURRENT STATUS AND CONDITION OF THE BUILDING 3.3.1 Existing Radiological and Hazardous Materials Contamination Specific radiological and hazardous contamination in individual laboratories is summarized at the end of the history for each laboratory. The enclosures for the pref':ter" and HEPA filters and the stacks for the hood exhausts can be found on tc. roof of the building. Parts of these enclosures are contaminated with I'dioactive material. Some of this material may have been released onto the roof when the filters were changed. The area around the openings to these enclosures must be checked for radioactive material and also for hazardous material if radioactive contamination is found. The hallways have remained unchanged since the building was first occupied. No laboratory activity occurred in these areas and there is probably no contamination in these areas. Most of the compressed gas cylinders previously utilized in EA1 (Bldg. 27) have been retumed to the corresponding vendors. The few gas cylinders which have 3-16

. -.. _ ~ ~. - - . ~ - -. _. ~.. -. - -. - l l l [ PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 l l been retained are currently in use to serve the various Proportional Counters or l Gamma-Ray Detector systems. Deionized water filter systems previously installed in the building have been removed. There are three air compressors serving the auxiliary air conditioners on the outside of the building, two on the l south side and one on the north side. The primary compressor serving the j' main facility ventilation system is located on the northeast side of the building. There are three air / vacuum pumps currently in service, two on the west side i and one on the east side of the building, which are used by GA Health Physics to draw air through filters which serve to monitor radioactivity in building air. l There is a vacuum pump outside of Rm. 27/111 which was used in the l operation of the Liquid Chromatography System. There is a large transformer i outside of Rm. 27/114, which provides electrical service in the fume hood in l this laboratory. There is an Explosion-Proof Refrigerator and Heavy-Duty Flammable Liquid Cabinet, situated in a metal enclosure outside of the l northeast comer of the building, both of which were previously used to store liquid organic chemicals. No residual radiological contamination is expected to - be found in this metal enclosure; residual hazardous organic chemical contamination is, however, possible. The controlled area parking lots on the west side of the building have been monitored for radioactivity on an annual basis and no hot spots have bwn found. Samples of soil from the landscaped ama south of the building were taken several years ago for use as blanks, but the concentration of *Cs and l "Co were somewhat higher than expected. 3.3.2 Physical Condition of the EA1 (Bldg. 27) Structure The general physical structure of the building is in good condition with two l significant exceptions. The first is that the roof has several minor leaks in the l area of Rms. 27/108 through 27/113 during heavy rain storms. Many of the i observed leaks are near Fume Hood exhaust penetrations. The second exception involves the control of the building Heating and Ventilation System. It is very difficult to control the temperature in the building, which requires a very l large flow of makeup air to compensate for the exhaust air flow, which is driven by the laboratory Fume Hoods and and equipment vents. GA Facilities Engineering organization has attempted to resolve this problem several times over the years, with limited success. The temperature in the laboratories in the t northem half of the building varies from 55"

85'F, depending on the ambient weather conditions. The temperature variation in the northem portion of the hallway may be greater.

4 3-17 l l e -

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 4.0 FIGURES FIGURE 4-1: EA1 (BLDG. 27) AND ADJACENT AREAS / /e

~

,,~.-:..'.'.... ( ,/ l g>s>'gq_. I 1 I I l~' N / L c'/&E'9]JL I y g m_ 3, g l [ Qm =- + Y l l [ h' N C .m L 4-1

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 FIGURE 4.2: EA1 (BLDG. 27) PLAN VIEW DETAll eg*

v v

M s l I l lc ?_ s i i n n C 7 :3 b o I I n_ w L J a l F a C l l 7 9 g_ d w J L r o a Z l 8 ( ) E S- _s t = a u ( II 3 E E C il JL N L J g ( I ) Ll [ JEL 15 O ~7 r Z a p 9 s o n cI i 3 n l __J -(. _ J 1. .7 I y v '1 J y v D l 5 i 00 e a J.,a e 3 c C. UU"i .3 11 E i L! /g .g 0 } = = 4-2 l

PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 l 5.0 . REFERENCES The information in this report was gathered primarily through direct interviews with individuals who were involved in various activities in EA1 (Bldg. 27). These personnel references are listed in Section 5.1. Additional information was obtained from the GA Facilities Engineering -l organization, in the form of engineering and construction drawings relating to EA1 (Bldg. 27); pertinent construction drawings are referenced in Section 5.2. l 5.1 PERSONNEL REFERENCES Individuals who have provided input for this report include the following: 5.1.1 D. W. Hill, (Author) GA Radiochemist, who has been assigned to EA1 (Bldg. 27) continuously from 1975 to the present. 5.1.2 T. B. Crockett GA Radiochemist, Manager of the GA Chemistry Group, and Principal Investigator for EA1 (Bldg. 27), from 1974 to 1996. 5.1.3 D, M. Fleischman GA Hadiochemist assigned to EA1 (Bldg. 27) from 1965 to 19f 5. 5.1.4 L. E. Kovar GA Radiochemist who worked in EA1 (Bldg. 27) from 1965 to 1973. 5.1.5 P. R. Maschka GA Health Physicist assigned to EA1 (Bldg. 27) from 1965 to 1973. 5.1.6 J. S. Greenwood GA Radiochemist who worked in EA1 (Bldg. 27) from 1974 to 1988. Currently assigned as the Principal investigator for the building. l 5.1.7 A. L. Greenwood GA Chemist who worked in the building,1985 to 1996. 5.1.8 S. P. Paguio i GA Chemist who worked in the building,1991 to 1997. 5-1

l PROCESS KNOWLEDGE REPORT FOR THE EA1 (BLDG. 27) LABORATORIES PC-000485/0 5.1.9 T. L. Tamoria - 1 GA Chemist who worked in the building,1988 to 1997. 5.1.10 K.1. Moore GA Health Physics Surveyor who worked in the building,1985 to 1997 5.2 GA FACILITIES ENGINEERING DRAWINGS The engineering drawings listed below constitute all pertinent design and construction documentation related to EA1 (Bldg. 27). Originals of these drawings are filed in the GA Facilities Engineering office in Bldg. 34. Working photocopies of each of the drawings have been acquired, and are stored in EA1 (Bldg. 27) for use during decommissioning operations. 5.2.1 GA Dwg. No. PE 27-8, " Site Plan / Floor Plan", General Atomics, San Diego, CA; revision dated 28 Aug 64; *as-built

construction drawing for EA1 (Bldg.

27); some of the originalinterior walls are missing. 5.2.2 GA Dwg. No. PE 27-29, " Piping / Ceiling Plan", General Atomics, San Diego, CA; revision dated 10 Jan 73; depicts the original floor plan of EA1 (Bldg. 27); the wall shown in what is now Room 27/114 did not exist. ) 1 5.2.3 - GA Dwg. No. PE 27 30, 'EA1 Building and Bunker Modification", General Atomics, San Diego, CA; revision dated 13 Jun 74; depicts the addition of the radioactive drains and Radioactive Liouid Waste Holding Tank to the EA1 (Bldg. 27) and the EA1-Bunker (Bldg. 271) facilities. 5.2.4 GA Dwg. No. PE 27-39, " Equipment Layout for Modifications", General Atomics, San Diego, CA; revision dated 25 Feb 74; depicts the EA1 (Bldg. 27) laboratory floor plan modifications, implemented in 1974. l l l I 5-2 i

lI lI 'I l ' APPENDIX B il To !I GA's Final Radiological Survey Report for 4 l Building 27 (EA-1) II i i I i " Building 27 Final Survey Plan" revised May 6,1998 I I I I I I I

I f May 6,1998 Page 1 of 7 March 6.1998 Revhed May 6.1998 ' A ' 9!wGonzales and Paul Maschka y,,.&& hud Nh5 { This mrvey plan is for Building 27 surfaces (building structure only and roof). It includes all former laboratories and office areas and a " footprint" area around the building. A soilsampiingplan will be prepared separately to sangpie the soll within the trench and underneath the building. k Final Survey Plan for Building 27 (Ernerimental Area) f This survey plan is for Building 27 surfaces (building structure only and roof). It includes all laboratories and affice areas of the building. Afootprint area aroundthe building willalso be surveyed. In addition, a sollsangplingplan will be prepared to sample the soil within the trench and underneath the building. Backpround and Classification Backeround Information f Construction of Building 27 (EA-1) was carried out between September 15,1964 and April 7,1965, on a site adjacent to, and immediately west of, the TRIGA Reactor Facility (Building 21). He building is of concrete masonry construction, with exterior dimensions of 41.3 ft x 112 ft (12.6 m x 34.1 m or-430 m ) 2 which houses an interior space of approximately 4400 ft2 (~405 m ). 2 The building was designed as a rectangular open shell with no internal load bearing walls. The only permanent interior concrete block walls enclose the small Mechanical Service Room, located near the center of the building east wall. f The building concrete deck incorporates a sub-floor Service Trench, ~2 feet wide x 3 ft deep (0.61 m x 0.91 m), situated along the north-south central axis of the building. The Service Trench accommodates ( installed service plumbing including, supply lines for domestic water, deionized water, natural gas, and I compressed air, and separate drainage lines routed to the sanitary sewerage system and the Radioactive Liquid Waste Tank, located northeast of the adjacent EAl-Bunker, Building 27-1. k The central Service Trench is crossed by one radioactive drain line (routed from room 27/109 to room 27/108). In addition, the radioactive drain line serving the sink in room 27/116 is routed through the cer. tral Service Trench, from the northern trench terminus to room 27/108. Most of the laboratories have been used for chemistry / radiochemistry work with the exception of the offices (rooms 100,103,104,105A and 105B) and the mechanical shop. Cl===ification (see Figure 1 attached) Each laboratory and the hallway between the laboratories were classified as " suspect affected areas". l 8 The Final Survey Plan was revised May 5,1998 for the following main reasons: 1. To include thefootprint area aroundthe building in the survey. 2. To revise / provide " alert levels"for instruments used. 3. Revise drawingfor location offixed measurements. WS (LAN\\EAl-BSP3.98

May 6,1998 Page 2 of 7 The office areas and outside walkways were classified as " unaffected areas". Affected Areas Former labs 101,101 A,101 B,102,106,107,108,109,110,111,112,113,114, 115,116 and all the hallway (except the small portion of hallway in the unaffected area). All internal walls have been removed. The affected area is an open area (see j figure I A). Unaffected Areas Rooms 100,103,104,105A,105B,(the small hallway and the mechanical room). See figure 1 and 2 (some of the internal walls have been removed). Outside sidewalk area around Building 27. l Survey Obiectives and Resnonsibility The purpose ofperforming a final survey is to demonstrate that the radiological conditions satisfy the NRC and State of CA guidelines for release to unrestricted use. The objectives include (1) to show that the { average surface contamination levels for each survey unit are within the authorized value, (2) to show that thi maximum residual activity (" hot spot" area) do not exceed three times the average value in an area up 2 to 100 cm and (3) that a reasonable effort has been made to clean removable contamination and fixed contamination and (4) that the exposure rates in occupiable locations are less than 10 pR/hr above background measured at I meter above the surface. Samples will be counted in GA's Health Physics Irboratory. Surveys will be taken only by qualified Health Physics Technicians having a minimum of 3 years Health Physics Technician experience following approved Health Physics procedures and this Plan. The survey and final report documenting the survey will be performed by GA's Health Physics group. 4 Release Criteria (ner GA Site Decommi==4mine Plan) } Facility Structure Criteria Concrete, soil and blastrac material samples were counted by gamma spectroscopy. The blastrac material represents contaminants removed from the concrete floor during aggressive decontamination. The result (blastrac material counted 2/24/98) showed 96% Cs-137 and 4% Co-60. One concrete sample (counted 2/2/98 collected from the floor showed no contaminants and the other concrete samples (counted 1/8/98 and 2/2/98 showed only Cs-137 contamination). Two other samples (a concrete sample and a paint I sample) collected in areas having radioactive contamination well above the release criteria showed no i evidence of contamination by gamma emitters or uranium or thorium. The most likely radionuclide c using the contamination is Sr-90. The applicable guidelines for residual contamination on building surfaces for beta / gamma emitters (including Cs-137 and Co-60) are: 2 2 5,000 dpm/100 cm, averaged over 1 m area 2 2 15,000 dpm/100 cm, maximum in a 100 cm area 2 1,000 dpm/100 cm, removable activity Alpha contamination was detected on equipment (which was removed and disposed of as radioactive waste); it was not detected on the concrete floor or other building surfaces. Preliminary alpha surveys of the concrete floor (after decontamination) using floor monitors were completed 2/28/98. No residual alpha contamination was found. WADMNTAl-BSP3.98

May 6,1998 Page 3 of 7 GA's intent is to decontaminate the facility to levels below the following Sr-90 release criteria: 1,000 dpm/100 cm, averaged over 1 m area 8 2 2 2 3,000 dpm/100 cm, maximum in a 100 cm area 2 200 dpm/100 cm, removable activity Ernosure Rate Measurements The guideline value for exposure rates measured at I m above the surface, is 10 pR/hr above background. Soil Criteria (soil limits anniv to eravel from the roon ~ The release criteria for soil (values are above background levels) is specified in the Site Decommissioning Plan and summarized below for the radionuclides ofinterest at or near Building 27. These levels also apply to concrete or asphalt tubble or gravel. Soil, asphalt and rubble must remain onsite; specsjic approval to remove ofsite required by NRC and/or State ofCA. Cs-137 15 pCi/g Cc-60 8 pCi/g Enriched Uranium (U-234 plus U-235) 30 pCi/g Thorium (Th-232 plus'Ih-228) 10 pCi/g Sr-90 1800 pCi/g If multiple nuclides are present, the sum of the ratios of the concentration of each radionuclide to its respective guideline must not exceed 1. Ifother nuclides are encountered, notify HP Managementfor release criteria. Soil was encountered during removal of the underground drain lines leading from the laboratories to the underground tank near Building 27. Cs-137 and/or Co-60 has been detected in the soil samples collected in and around Building 27. Gross alphalbeta results are requiredfor a representative number ofsoil samples (to have an upper bound for the maximum Sr-90 concentration which could be in the soil). Sr-90 analysis may also be required. Alert Levels If the following " alert levels" are exceeded, notify HP Management so an evaluation can be performed to determine ifincreased survey coverage or decontamination is required. On Concrete or Asphalt Surfaces l Note: Alert levels for other surfaces can be estimated as the background cpm plus the cpm value provided below for each instrument type]. Aloha Monitoring 2 > 100 cpm alpha using the large area (434 cm ) probe. (If>100 cpm, check with hand-held a meter.) > 60 cpm using a hand-held alpha probe, notify Health Physics Management. 2 Beta Scanning using the 434 cm probe 2 > ~1900 cpm beta using the large area (434 cm ) probe (#84459) 2 > ~2300 cpm beta using the large area (434 cm ) probe (#73701) WDPLAN\\EAl-BSP3.98

-~ l-May 6,1998 Page 4 of 7 > ~300 cpm above background of another 434 cm ) probe - make sure the background determination has 2 been completed at Building 13 (or other HP management approvedlocation) Alert LevelExceedence during Beta Scanning-To determine if additional decontamination is necessary in areas where the alert level has been exceeded, the following should be performed (both inside the building ud sidewalk outside the building: 1 At the 10,1 m grid locations which had the highest floor monitor readings, scan the 1 m grid using the j 100 cm2 probe (for each instrument). If readings are > 650 cpm, decontamination may be required; i notify HP management. If readings are < 650 cpm, no further decontamination is needed; this represents ~200 cpm above background (400 counts for a 2 minute count), i 2 Beta Measurements using the 100 cm orobe > ~1300 counts in 2 minutes using the beta 100 cm gas flow proportional counter (s/n 84423) 2 > ~1150 counts in 2 minutes using the beta 100 cm gas flow proportional counter (s/n 86332) 2 > ~200 cpm or 400 counts in 2 minutes above background for other beta 100 cm gas flow proportional 2 i counter or if probe calibration has changed or of other changes to the meter have been made -- l make sure the background determination has been completed at Building 13 (or other HP management approvedlocation). l~ Decontamination Required - When (1) GM measurements > 150 cpm or (2) values greater than l those provided above using the 100 cm probe. 2 l Ernosare Rate Measurement - Alert Levels Exposure rate measurement measured at I m above the surface - 5 R/hr above background or above 20 l R/hr,which ever is less. On Soil / gravel and at*=lt and concrete rubble l Any radionuclide above natural background levels (see HP-40 for background levels). All soil sample L results must be reviewed by Laura Gonzales or Paul Maschka. Site Conditions at the Time of Final Survey l Process equipment and supporting fixtures were removed from radiation restricted areas and cleaned and l released or disposed of as radioactive waste. All " suspect affected" concrete floor areas were decontaminated by grit blasting. Remaining contaminated surfaces (identified by post decontamination l surveys) or walls have been decontaminated or surfaces removed and disposed of as radioactive waste. l Lower west wall decontaminated by removing sections of this wall, therefore, more surveying is required. Documentation Every survey conducted must be documented on a daily basis on a drawing showing the approximate locations surveyed. Include the results (including units), the technicians signature, date, instrument (s) used i (including model and serial number of both the ratemeter and the detector), calibration due date, % efficiency, background readings (if applicable) and any other applicable information. i I Q\\D PLAN 4Al-BSP3.98

l l May 6,1998 Page 5 of 7 Planned Surveys for Building 27 (Experimental Area) Unaffected Areas (Rooms 100,103,104, 105A,105B, the hallway Unaffected area Type of Survey Affected Areas between 103/104 and Sidewalk around the 105A/105B and the Buildingm Mechanical Room Concrete Floor W 100 % a,100 % p 100% a,100 % p 100 % a,100 % p 8 (Scan w/434 cm probc) Lower Walls Scan 100 % a,100 % p 10%a,10%p Only above areas found to be (bottom 2m) contaminated 8 (Scan w/434 cm probe) Walls Scan (tbove 2 m) 25% a,25 % p m West Wall 10 % a,10 % @ Not Required Not Required North Wall 10 % a,10 % p Not Required Not Required 10 % a,10 % p Not Required Not Required South Wall East Wall Not Requtred Not Requtred Number of Planned Measurement every ~2 m Measurement every ~4 m Measurement every ~4 m W Measurementsm H) Alternate between (1) a See Attached List removable and (2) a beta fixed measurement on the floor

Paint SamplesW 4 each on east and west wall None Required None Required 2 each on north and south wall R/hr Readings I every 3 m i every 7 m i every 7 m

@ im from surface Floor Drains 7 Floor drains in trenches (see None None Soil Sampling Plan) Floor Surface Concrete Concrete or Tile over Concrete Concrete Roof Collect gravel samples I per 50 m (evenly spaced throughout the roof) 2 Additional samples may be taken m biased locations also. [Obtain approval from A. Lewis and L. Alfonso to be on the roof and follow safety instructions) ampling To Be Determined - A Soil Sampling Plan is Required per Site D Plan (gamma spec required on all samples; gross alpha / beta required on some samples) WAD-PLANIAl-BsP198

May 6,1998 Page 6 of 7 l 'W Clean all surfaces to remove debris or dirt (wash, mop and/or vacuum, as needed). l Grid in a 1 m grid pattern. W The west wall (below 2 m) was contaminated. Therefore, more coverage to the upper walls (above 2 m) will be given (at least 25% of the area will be scanned). In addition, scan 100% of all decontaminated areas and the surrounding area (at least 2X the size of the area decontaminated must receive 100% coverage). Document range of results for each j location.-

For the fixed measurements:

l - For a measurements; use either the hand held alpha counter (~5-10 second count). l Document all readings in cpm. l. 2 For p measurements; taki.; a 2 minute count using the 100 cm gas flow proportional j. detector (beta) with the Model 2221 ratemeter. Take additional 2 minute beta measurements in selected decontaminated areas of walls and other areas. Document all readings and mark on a drawing where the readings were taken. Take fixed measurements on wall ~1 meter from floor surface. 2 ") For removable measurements, take a 100 cm wipe at each location and count using a low level alpha / beta counter. W A 100 cm paint sample will be collected from the lower walls (about I m from the floor). A 2 2 2 minute fixed reading using the 100 cm beta detector and Model 2221 ratemeter will be taken before l and after paint removal. ") 100% coverage is required in decontaminated areas and the area surrounding this location (out to 2 m from the location); take fixed measurement (s) in decontaminated area. Check with GM counter j also. 1 L l W:OPLAMEA1.BSP198 l

I May 6,1998 Page 7 of 7 Estimated Number and Locations of Fixed Measurements and Smearsmm Location Estimated # of Fixed Estimated # of Smears Measurements 2 Affected Areas (~330 m floor area) Shown on Figure 2 Floor 44 Floor 44 Former labs 101,101 A,101B,102,106, Walls 2.1 Walls 24 107,108,109,110,111,112,113,i14, Overhe vi, Structures 10 Overhead Structures 20 115,116 and all the hallway (except the I-beam, 10 I-beams 20 small portion of hallway in the Lights 5 Lights 10 Miscedaneous __1 Miscellaneous J.Q unaffected area). Floor-330m: 97 128 Walls - 184m2 Unaffected Areas inside building Floor 10 Floor 6 2 ~76 m floor area Walls 8 Walls 8 Shown on Figure 3 Overhead Structures 0 Overhead Structures 4 Rooms 100,103,104,105A,105B, the I-beams 0 I-beams 4 ) hallway between 103/104 and 105A/105B Lights 0 Lights 2 l and the Mechanical Room). The walls Miscellaneous _Q. Miscellaneous _2_ between 100,103 and 104 have been 18 26 removed (it is now one open room). Unaffected Area-outside sidewalk Floor 26 Floor 9 2 ~100 m sidewalk area Shows in Figure 4 Total Number of Measurements 141 163 Roof Gravel Samples Take 10 gravel samples in the approximate locations shown in 2 as shown on figure 1B (~1/50.n )- additional biased samples may be taken. A " measurement" is either (1) a " fixed" radiation measurement representing total activity or (2) a wipe (removable activity). m Additional fixed measurements should be taken at selected decontaminated areas of the floor and i walls. Additional Surveys l 1. If contamination is detected in unaffected areas, an evaluation will have to be performed and the classification reevaluated accordingly. 2. Additional gravel samples may have to be collected if the concentrations are > 10% of the guidelines are detected. 3. Tar samples from the roof may have to be obtained if gravel samples are > 10% of the guideline values. l I l W:\\D.Pthf4Al-BSP3.98 i

M sassemwwweisusus+ U a n Omotme newanes N 3 O 5g Wo ,~~~ H H Y O v n j = = = H sm. C ] h H H H H H H e 3 ( ,) C I 8 a 3 H H S = N = 2 3 p. H H $5 Qt O D E 4 e 3S zwuzcz-u<s, g* 8 E k H m H (" .C h* "( gi, kI ( ) ( ) II M H a. W m "4 ,! j E 5 E 2 =a. 4 .- )

.t 2

H H a = I'5 3a a 2 a:* 3 /\\ bA ~ I o H H A,

l i I t 6 10 , a D w m - d 73 63 N 43 3 7 23 13 3 02 3: 7 2 8 r 2 o k 0 y 4 n 2 e r 1 3 r 2 o 2 w 2 k 12 O 9 1 8 1 7 ~ 1 6 f 1 ' / 5 1 / 4 1 / 3 1 2 1 1 s 1 M m o t y 9 "^ 8 7 6 5 4 , n w m 3 2 d s v. 1 A 1 ig f J K L M N o P Q R S T U V W X A B C D E F G H g

,\\.I l l ll\\lli iI l1! l 0 '4 es e's ~- a 73 s s 's 4 ~' s 3 a e '3 's 1 0 '3 s 'a u s a 7s'es

s a

sa sa se s lp m 1 3 as 03 l s e i va s r 1 g 71 fo s 1 s 5 n 1 o 4 i 1 ta 3 c 1 o ) 3 l 1 1 1 e A 1 E ta ( C m 7 i 2 x 9 or .g ld p 8 p B A 7 too 3 6 R 5

C4 e3 ru 2

g iF d 1 s v. 8 A 1g A B O D E FG H J K L P Q R S T U V W X I i{l ll

x [h S '= 0 0 0 Iib e O { 4 O O O e O O O 2 (- M O O O O O O O O x O O O ,0 0 0 0 O (~ 2 O O O O O O O O 2 g O O O O O O o O N q n O e O O O e O O = J I~ N o O O O O O O O U I e O O O o O e N I O O O O O O O 2 2 O O O e 0 e 0 e 't c O O O C G e s e N [E s 5 o o O O c o i 2 \\ je o O o O c 0 1 - c. O A: O O O O E 3 0

O'

- 2 ) 'j O O O O C s O [l - O e O O E O \\ O O O O C O M O 5. O o Ille c d { e; o ~~ l] e 1 Ih !~{ 00 g < m o c w w o z x a s z o a o m m e s > 3 x I

e -W A I1 .S N XT Figure 3: Unaffected Area Bldg. - 27 (EA-1) As of 05/06/98 v s 1 2 3 4 5 6 7 8 9 to 11 12 13 14 15 16 17 18 19 20 + A B l { C i LJ ! O LJ ! O a e o o o-D n WiE v -( 3 ph, Q f w=n Q h D le G 5 0 ~ J o 0 o H I r1 ! o r1 I o o m w.a w,a w,. we g J I K L M l 1m MM O - 100 cm2 wipes 0 - 2 minut. vix.a m or.m.nt.

shvad E.......

. - - _..... =.

i + __. A s c D F a H l 3 g L u N op o R s T U y W X l 04 04 9 e 3 s })6 3 e s o O 7 73 3 6 O O O O e 3 s O O 6 s 3 a 4 3 43 3 3 3 3 fI 2 2 3 3 O O 1 1 3 3 0 o 3 s 9 O 9 2 2 8 e 2 2 O O 7 7 2 2 '6 s 2 a 5 5 2 O 2 4 4 2 O l 2 l 3 s O 2 2 2 2 2 2 1 1 2 2 ) 4 fI 0 A 0 2 2 E w O t O "- 9 o 7 1 t 2 m 8 1 e G o 'e t E 7 7 L 1 B 1 6 o 1 t O O s 5 1 i 4 4 1 f 1 3 O s 1 i f 2 2 1 1 O O 1 1 1 1 0 o 1 t 9 s 8 f a O O m 2 7 7 6 a 5 C

0 s

4 4 O O d 3 3 n v. O O O O 2 2 N 4 O O ig F w4 1 1 E S A B C D F G " J K M N O P o R s T U V W X l ~

\\ APPENDIX C i To i GA's Final Radiological Survey Report for Building 27 (EA-1) " Final Trench Survey and Soil Sampling Plan for Building 27 (EA-1) " revised May 15,1998 and Addendum 1 " Revised Final Trench Survey and Soil Sampling Plan #1 for Building 27 (EA-1)" revised May 15,1998

l May 15,1998 Page 1 of 7 May 9,1998 RevisedMay 15,1998 b La Gonzales/ Paul asc p g4 NMJ Finni Radiological Trench Survey and Soil Sarnnling Plan #1 for Building 27 Introduction and Revi=ians to Plan ne May 9,1998 Plan covers the radiological survey of the concrete lined trenches in Building 27 (EA-1) including the survey of the drains, pipes and other items inside the trenches and the sampling of debris / sand / soil presently inside the concrete lined trenches. It also included a Soil Sampling Plan for sampling the soil underneath Building 27. It does not incInde senqpling soll around thefacility. During implementation of the plan, the following was identified (including what action to take). (1) The HP Technicians started implementing the Final Trench Survey and Soil Sanspling Plan

1 (dated May 9,1998). Contamination has been found in one section of the trenches (grid area JKLM @ 21/22 area); an area about 4' X 3'. He contamination levels are ~ 25,000 dpm/100 cm2.

(2) Other areas of the trenches were scanned using a GM counter and the 100 cm probe; no 2 centamination has been detected. (3) He " hot drain line" was removed but the line also went east to a main drain in the middle of the main trench. (4) Hot water line insulation should be checked for asbestos (on Alan Lewis was informed that C. Stanley had discussed the insulation with the asbestos abatement crew and that it probably was not asbestos). (5) A meeting was held on May 12,1998 with A. Lewis (who has delegation while J. Greenwood is on vacation), G. Bramblett, J. Tumer (who was assigned effective May 9,1998 to discuss items (1) through (4) and action to take: It was decided to (1) remove the pipes in the trenches, (2) remove the debris / sand / soil from the trenches to allow us to scan / survey the bottom of the concrete lined trench and (3) to remove the remaining pipe that extends from what was the original hot drain line. Contractors are at Building 27 right now doing this. l-Note: Of the 7 debris / sand / soil samples collected from the bottom of the concrete lined trench . (in accordance with the Plan),4 showed only background radionuclides and 3 showed low !cvels of contamination; I had Cs-137, I had Cs-137 and Co-60 and I had Cs-137, Co-60 and l U-235. The levels were below GA's release criteria but the debris / sand would have to stay on I the GA site (unless additional NRC/ State approval was obtained). Therefore, it will be I disposed of as radioactive waste. j (6) Concrete cutting began May 13,1998 for soil sampling under the facility in accordance with the Plan. f

( May 15,1998 Page 2 of 7 (7) One soil sample underneath the concrete (S30 in Plan) has been collected and analyzed; no contamination was detected. This sample was collected from an area which had beenjack-hammered deep enough to expose soil. Classification and Additional Survey Coverage A drawing showing the rooms and laboratories prior to decommissioning is provided in Figure 1. The concrete lined trenches within the building and the trench formed after removal of the f underground drain line are shown in Figure 2. The trenches were classified as "non-suspect affected areas" as well as the soil underneath the building. After clean out of the trenches has been completed (removal of all piping and debris / sand / soil); the trench will be surveyed as follows: 1. The known contaminated area (includ'ng the area surrounding these grids) will receive 100% survey coverage. 2. Survey coverage for the rest of the trench will be increased from 10% to 50%. 3. Measurements will be increased to "a measurement every 2 m"(alternate between a wipe and a 2 minute beta fixed measurement). 4. Increased alpha survey coverage from " spot check" to 10%. 5. The sampling of soil undemeath the building will remain the same except samples #10 f and #14 can not be obtained (the bottom of this trench is concrete because the hot drain pipe was enclosed in concrete before removal). Bacharound Construction of Building 27 (EA-1) was carried out between September 15,1964 and April 7, 1965, on a site adjacent to, and immediately west of, the TRIGA Reactor Facility (Building 21). The building is of concrete masonry construction, with exterior dimensions of 41.3 ft x 112 ft 2 (12.6 m x 34.1 m or ~430 m ) which houses an interior space of approximately 4400 ft2 (~405 2 { m). Most of the laboratories have been used for chemistry / radiochemistry work with the exception of the offices (moms 100,103,104,105A and 1058) and the utility (also called mechanical) room. The building concrete deck incorporates a sub-floor Service Trench, ~2 feet wide x 3 fl deep (0.61 m x 0.91 m), situated along the north-south central axis of the building. The Service Trench accommodated installed service plumbing including, supply lines for domestic water, deionized water, natural gas, and compressed air, and separate drainage lines routed to the sanitary sewerage system and the Radioactive Liquid Waste Tank, located northeast of the adjacent EAl-Bunker, Building 27-1. / L (

l l l ~ May 15,1998 Page 3 of 7 l ne central Service Trench was crossed by one radioactive drain line (which was routed from former room 27/109 to room 27/108). In addition, the radioactive drain line which servicid the sink in room 27/116 was routed through the central Service Trench, from the northern trench terminus to room 27/108. Figure 2 shows the existing trenches. i l De trenches are for the most part concrete lined with the exception of trenches caused by the l removal of the underground drain lines that went from the a few of the laboratories to the j underground radioactive liquid waste holding tank (which is still located behind Building 27-1). l Many of the concrete lined trenches were found to be partially filled with sand / soil or have debris covering the bottom of the trench. Figure 3 shows the locations where debris / sand / soil samples will be collected inside these trenches. f i l Figure 4 shows Soil Sampling Plan #1 for soil samples to be taken undemeath the "affected" area of the building. Some samples are to be taken in exposed soil locations and in jack hammered areas. Concrete will be cut out in some areas to expose soil for soil sampling in other areas. This soilsamplingplan does not include soll sampling outside the building. l Survey Obiectives and Da=na==ikility i ne purpose of performing a final survey is to demonstrate that the radiological conditions of the soil and the trenches satisfy the NRC and State of CA guidelines for release to unrestricted use. The ( objectives include (1) to show that the average surface contamination levels for each survey unit are within the authorized value, (2) to show that the maximum residual activity (" hot spot" area) do not exceed three times the average value in an area up to 100 cm and (3) that a reasonable effort has 2 been made to clean removable contamination and fb:ed contamination. Samples will be counted in GA's Health Physics laboratory. Surveys will be taken only by qualified Health Physics Technicians having a minimum of 3 years Health Physics Technician experience following approved Health Physics procedures and this Plan. The survey and final report documenting the survey will be performed by GA's Health Physics group. Release Criteria (ner GA Site Decom>=i==ionina Plan) Facility Structure Criteria The release criteria for the concrete and other items in the concrete lined trenches is: 2 2 1,000 dpm/100 cm, averaged over 1 m area 2 2 3,000 dpm/100 cm, maximum in a 100 cm area 2 200 dpm/100 cm, removable activity Soil Criteria ( The release criteria for soil (values are above background levels) are specified in GA's Site (- Decomrnissioning Plan and summarized below for the radionuclides ofinterest at or near Building 27. These levels also apply to concrete or asphalt rubble or gravel. Soil, asphalt and i l

May 15,1998 Page 4 of 7 concrete rubble (above background) must remain onsite; specifc approval to remove ofsite requiredbyNRC and/orState ofCA. Cs-137 15 pCi/g Co-60 8 pCi/g Enriched Uranium (U-234 plus U-235) 30 pCi/g Thorium (Th-232 plus Th-228) 10 pCi/g Sr-90 1800 pCi/g If multiple nuclides are present, the sum of the ratios of the concentration of each radionuclide to its respective guideline must not exceed 1. Ifother nuclides are encountered notify HP Managementfor release criteria. Soil was encountered during removal of the underground drain lines leading from the laboratories to the underground tank near Building 27. Cs-137 and/or Co-60 has been detected in the soil samples collected in and around Building 27. Gross alphalbeta results are requiredfor a representative number ofsoil samples (to have an upper boundfor the maximum Sr-90 concentration which could be in the soil). Sr-90 analysis may also be required Alert Levels If the following " alert levels" are exceeded, notify HP Management so an evaluation can be performed to determine ifincreased survey coverage or decontamination is required. On Concrete Surfaces Alnha Monitoring (Spot checks only) > 60 cpm using a hand-held alpha probe 2 Beta Measurements using the 100 cm nrobe > ~1300 counts in 2 minutes using the beta 100 cm gas flow proportional counter (s/n 84423) 2 > ~1150 counts in 2 minutes using the beta 100 cm gas flow proportional counter (s/n 86332) 2 > ~200 cpm or 400 counts in 2 minutes above background for other beta 100 cm Eas flow 2 proportional counter or if probe calibration has changed or of other changes to the meter have been made -make sure the background determination has been completed at Building 13 (or other HP management approvedlocation). Decontamination Required-When (1) GM measurements > 150 cpm or (2) values greater than those provided above using the 100 cm' probe. On Soillernvel and aanhalt and concrete rubble Any radionuclide above natural background levels (see HP-40 for background levels). All soil t_ sample results must be reviewed by Laura Gonzales or Paul Maschka. L

May 15,1998 Page 5 of 7 Surveys and Samnling to be Performed Caution: Acid fumes are present in the trenches (especially along the north to south trench) and sewer smells are noticeable. Alan Lewis and Letty Alfonso were contacted for proper safety precautions to take before surveying. Type of Survey Survey / Sampling to be Performed Scan with 100 cm2 Holra All pipes inside the trench removed and disposed of either as radioactive waste detector (where feasible) r " clean" waste (aaer survey showed levels were below the release criteria). 1. 100% p in Grids 20-23 and JKLM o erwise 2. 50% $ for the rest of the concrete lined trenches (sides and bottom). 3. 10% a along the sides and bottom of the concrete lined trenches. 4. 50% p on bottom of hot drain line trench. 5. 10% a along the bottom of the hot drain line trench. 6. Scan areas where spills or stains on the concrete are noted. NumberofPlanned 1. Take a measurement every - 2 m along one side of the concrete lined trench. Measurementsm (2) 2. Altemate between (1) a removable and (2) a beta fixed measurement. Debris / Sand / Soil Sampling Nntra Debris / sand / soil from inside the trenches will be removed before survey of the concrete lined trenches. The debris / sand / soil will be disposed of as radioactive waste. 1. Some areas of the concrete lined trench are filled (or partially filled) with debris or sand or soll sand. Seven (7) samples will be collected; see sample locations in Figure 3. (COMPLETE) 2. If contamination is detected on the concrete sides of the trenches or in the debris / soil / sand itself, it may have to be removed. 3. See attached drawing (Figure 4) for locations (31) where soil samples (total of 36) will be collected from undemeath the building and underneath areas where the concrete will be removed. A list providing a description of the location and type of sample to be taken is provided below. 4. A gamma spec is required on all samples; gross alpha / beta required on some samples (to be determined). Exposure Rate Monitoring 1. The exposure rates in pR/hr must be monitored on the surface of the soil and in the trenches (especially the soil lined trench where the drain line was removed) and on the surface of the soil after concrete removal. j 2. Report any level > 20 pR/hr (at I m above the surface) and > 25 pR/hrmside the concrete lined trenches -- to IIP Management. W For fixed measurements: For a measurements; use the hand held alpha counter (~5-10 second count). Document all readings in epm. 2 For p measurements; take a 2 minute count using the 100 cm gas flow proportional detector (beta) with the Model 2221 ratemeter. Document all readings and mark on a drawing where the readings were taken. 2 W For removable measurements, take a 100 cm wipe at each location (count using a low level alpha' beta counter. l

. - - ~ - May 15,1998 Page 6 of 7 Soil Samnle Locations Underneath the Buildine (See Finure 4) Summarv A total of 36 soil samples will be taken in 31 locations (in some locations, both surface and subsurfaces samples will be collected). This represents about 10% of the entire "affected area" including the areas having the highest potential for soil contamination. 81, S2 and S3 are to be taken underneath the concrete after removal of the concrete (grids 15 - 19): S1, S1 A O Surface (0-6") and subsurface (6"-12") grab samples S2 O Surface (0-6") grab sample S3 O Surface (0-6") grab sample i 84 and SS are to be taken underneath the concrete after removal of the concrete (grids F 8/9-G 8/9): S4 O Surface (0-6") grab sample SS O Surface (0-6") grab sample S6 and S6A will be taken in a soil exposed area along the west wall (grid E/F 21): S6, S6A O Surface (0-6") and subsurface (6-12") grab samples S7, S8 and S9 are to be taken underneath the concrete after removal of concrete (grids F/G/H 23/24): S7 O Surface (0-6") grab sample l S8 O Surface (0-6") grab sample l S9 O Surface (0-6") grab sample S10, S11, SI1 A, S12, S13, S14, S15 and S15A are to be col!.ected inside the trench formed after removal of the radioactive waste drain line which went from the labs to the underground liquid waste tank. Some samples are from the bottom of the trench and some will be collected underneath l the existing concrete. Both grab and composite samples will be collected: S10 0 Surface (0-6") grab sample from the bottom of the center of trench (cannot be taken; bottom is concrete) S11,SI1A O Surface (0-6") and subsurface (6-12") grab samples S12 //// Composite sample from the south side of trench (directly underneath the concrete) S13 //// Composite sample from the north side of trench (directly underneath l the concrete) S14 XXX Composite from the bottom of the trench (cannot be taken; bottom ) is concrete) S15, S15A O Surface (0-6") and subsurface (6-12") grab samples S16, S17 and S18 - underneath the concrete after removal of concrete (grids F/G/H 33/34): S16 O Surface (0-6") grab sample S17 O Surface (0-6") grab sample S18 O Surface (0-6") grab sample l

May 15,1998 Page 7 of 7 S19 and S19A'will be taken in a soil exposed area along the west wall (grid E/F 37): S19, S19A 0 Surface (0-6") and subsurface (6-12") grab samples S20, S21 and S22 - undemeath the concrete after removal of concrete (grids O/P/Q 34/35): S20 O-Surface (0-6") grab sample

S21-O Surface (0-6") grab sample

~S22 .O Surface (0 6") grab sample t S23~.O Surface (0-6") grab sample from underneath recently jackhammered concrete floor area (Jackhammer to soil) S24, S25 and S26 - underneath the concrete after removal of concrete (grids O 23 through 26): S24 O Surface (0-6") grab sample S25 O Surface (0-6") grab sample S26 .O Surface (0-6") grab sample S27, S28 and S29 - undemeath the concrete after removal of concrete (grids O/P/Q 20/21): S27 'O . Surface (0-6") grab sample S28 :O . Surface (0-6") grab sample S29 O Surface (0-6") grab sample S30 and S31 are to be taken in the jack hammered area (soil is slightly exposed already ~ J 22/23): S30' O Surface (0-6") grab sample from underneath recently jack hammered concrete floor area (soil slightly exposed) S30 O Surface (0-6") grab sample from underneath recently jack haramered concrete floor area (soil slightly exposed) Documentation Every survey conducted must be documented on a daily basis on a drawing showing the approximate l ' locations surveyed. Include the results (including units), the technicians signature, date, instrument (s) - used (including model and serial number of both the ratemeter and the detector), calibration due date, % efficiency, background readings (if applicable) and any other applicable information. l

l l \\l Il1' jj! \\ l lj 1 ,I 7 2 -C l B C ,_) C C ~ i l 8 D -D l l E gI I 8 1 Z ( 1 er 4 5 6 u 1 1 1 1 S g i 1 1 1 F V L t 2 3 1 1 1 1 1 E 0 l 1 i 1 t mo 3 o Z R lac ina 8 9 h 0 0 s 1 e 1 it dn z a Z 350 P A 6 7 05 0 0 1 ) 1 1 A 1 ya e 1 w r Z l u l g a i h F R0O 4 e 0 e 1 S / ( H^ I' 30 a 1 e r 1 2 . a 4 40 d 5 1 e 0 0 o 1 .t g 1 c 3 e 0 f 1 f g 1 e .a 0 t 0 c f [ ( p a s m u o s n 5 o a 1 R e l P B A r o 1 1 3 e t y 0 0 0 ' a r g m e 1 1 v 1 o n r f i e d s e l ) r i s 7 R_ a v 1 2 h s e E g a e r n 1 e h u M. i 1 r t g d a i l H f r i 1 0 T d o u 0 0 R e B 1 t t. 1 O c s s l N e e ( a f r n f f. i a e F . h o t' T n z y 1 r Ij)

ZY" l < m o o m ua e t :, w _i _.g n2 _.4,__.p4_+aa_s z o e a m m v a' s s: x g wn2 +j, _1-i i i .~ - -4 _ p.,d _.~ _ _. -...._,l J _ _. 5- _ - --y- ~ 1 1 i i I t I.. i l._ i!

y... __v_i y

_. ~.~. g!3-i i _S_...._1+..,.. J. !_.J.- ~ _4'_.-.7.- +-.g. _!* _$. f_ _ _l' l . _.p..d_ l... 7-.m _.e --.- i i 4 i l l l E - p +._._4-4_ l ._{ } ' l i I ! I MS... _ - E i _.__J. __ _ 4. v. i +.4..- ._;_p_ 4 _ l l i i ~ _n. q 1 - - - --_s_7 1 - N yg4_.-)- -+-t_ yf=. 1 l -g __._...__L t i i i. i _ 4 J_.[' ah._ }'_ .__q. _p.-p -.- -4. _..t " .. c )_ p'.. { _l = t '* q 4.g' g--... 1--_ zpa-. - -.u - - +.-.+-+- i t d ln / -.h._.. ._j_ ...p -v_. I .N ] _ 1_ " ' M_ _a._._i_r_._._ _ j y'_4.---t - ,3 y.y _ _ t_ _a. _B_ _4_ h_ 1-- * -90 J_ __... p t-2L4 a,;__ i i ej 1I _i_.Ig gg,l p!- _-..i -s e.y-j ,._.L ; a

y.a i

i i 4, 7 4_.. .m,._.. l ! N ) _._._._j_ ] _ -b ~ i i I 4-d- ~ - } -- k-- 4' b~- .-.r - M l l 2 4._.LA _ vl }_%l _ _ t +1.+. N I l l 4.. _.l 7.. y

__4 _ yl_ 4 _.-

3. U j_,_.}_..._,l_.r 7 i ._7_4 _..., y. _ ;3._.~t i a t ~ 1._I i l_.g 8 l i.~i_ ~~! _J _ _ e. _ I._yy _a a _a__ i _t._ . _ _ _ _L. - g .__4_ _._+_,I_ s ..1 s t -_a.,i iy,_ _i _.. _,I.4_,.._m 4_ i la y j" q!_..- .__.p_ }_ __W i i i a.,l_4 ,i _ ._n _ 1,i4. !. i a t y q.__ g.g u _g e 7.. g-1 y_+- ll _e_.i . 1 _ l_..l Ir!}! 1m,- e I , _.4 _.f _tH._ ! _.4 1.*"- 2 l .2 __ 4._.+l . _ _._7 2 _i..+ l, l 12 I 4 7N N l [ l f ] ] .}. 3 _L_ __1,.__ !_ g, j _ a _ a _. _. g. qI - gr.._ ~_ a_ r, _._y_ c .w f I a g _*__ .p_.T_ . _. _.._4.._ I i i _gw 4 i,._ ..4.... _..._ - 7,. _4 _. _ _. _u w .p_. 4 - b b 7 q.__ ._.7 7_ qq_ _f_lt.a_f dq3 y _ _+ _ N

l l

e 0 .,,,,... ~... ..-.4 Y -ye ..y. m.- l j 1 l.._ l O _. ! 4.[ n 3 In l -g i al p Lp' l_.._ a i j u I- ,_._L-..-s-I ! _L. 2.A +_.1_,i_I. l ! i J e _x I-4-v.,-_.,4 a l ( ! ! ! l F- .t J p--Q._-4---]- M- -l g re r 1-H-e

_4__.._. _ _ __1

.. _ e, . 41 Q ~ i (3 < m o a w u. j e I , x s z io a. j o y m s a > 2: ! i g lx m

W Figure 3: Trench Debris / Sand Survey Plan for Sidg. - 27 (EA-1) As of 05/0W98 n S N j t 1 . i ! j 1 ;2!34 5 i [ 6 ; 7 l 8 i 9 ! 10 ? 11 !12 13 14 15116 17 18 19!20i.21 22l 2324 25126i27 '28 f29 l30 >31 :32 l33 34 g i : 1 t e i i i a i 35 ;36 !37 l 38!39140 i j ',- .4. _4._-.a_._.-4_ 5 _1__.4 i 4 i 3 -.w.__.g 4_

4. _+ __

._ 4

4 4

- : ' i i . i }' j I i i { f i i i i 1 I i i

I i

( t I t 1 i t i, t j i ' 4 l t 'I "i l I l i ! I j l ! l ! i i I i i i l l l i ' -+ 8 i -- W ---- 4-------*---+--,--+- +----+--+t A : 4 p j! + - - - - + - .i i i : ;, i r 6 a._ 2 f l w__4___ A.- 4 _ - __j_..p_ 9 _ _e __p g ,_.y _.. r _l.__.M l 1 I t ! i - r_+.__+ B

i I f I ' '

_ 4 _ L' _4 _4_ y.__,._ ;__. p _,i L__...(.._ ;. - 1 _4__p w _+___ b 4_ " ' i i. i i. > i ' i i ! ' .+ _4 l ' ;B 4_ _J t

4_._;_. _4 _2._4_

i ' ' ' ' C .,i ii I I 'i i ' i ' , i ' i i ,._._,i__t_.+. ' i i i 1.- _ i _+ t__,- __ ! ,i. _._C. 4.__.+_ ~ 5 . i - _~ . i i ! ' : i : - 1

i,

D i i 1 l _+l i ' i 1'

i i

3 l .i.w.g._-..-..i_4 p ?._, t _+_ 4 +i _A i I i a i 5 i_,.,___y 1 _--i_ l 4 1 i ~.; + a D s _-{ ~-- % _,i. i. t. ! ! l +! i ! ! ! ! +! i ! i i ! l ! ! t i ! E l _.w._+ -_~..,! _iE F l . ; j !

-- j.__

_. ! j l l {' __rl __+l l ! i ! j 1 9__'m__{._._{y

': I 1.___7_j p

y _._.+._4_.4 G + i i I I i 7 ,_.-+. .._ M ,.._4-_,..1_._ _ ;__I_.i _._._ L m_i d'., l r l' _ i _.._ ]- y__,._ 4.__l .j._ 4_.4 _ ' 5 ! i = i 1 ) + _- i_ _! .1._ f i 4ma.4 l _ _t - _! ! i ! i I i I l i ; ' o! ~k_?_O. i H : ! ' i _2_.!_%2_..j_ aml i ! ! i 1 _4._4_+ .s _a _u.__% . _ _ + - + > i i i i '. H s % _l B, LDG.2,7 /EA-1) .,_.4_ l 1 i ! i r. 1

, i i

t .' ; i ~ l i I j -. a - u 7._ - i i _.,I_ 4 ) . l- + 4 _._t- -. 4 A,.__ 3._ 4. i.d. 2N .. i_. _ i_ jM i IC! -..j._. K ! l'. S p h a! I mgyi. 1 G.as h' w A2A - - y2 4 i I i i ! I ' i t ! ' 9; K_ t M - - L_ u.__; m_ _._. 4_.u L me, !. _5 2_ w. w t ir

. ~ ;

i t

a r

i i. - n i l i i .a..M,. i _.4_.M__._% ! _.4 _ ; _.sl .. ?.i,. __ : j c i g ; t 4 i 3 t i '.~ 1 I r f t l _4_2 + i i s f 2 i i . + _. -... _. +. 4 -M N * , _ _ _ + _ -.m.. e t ' i _.i J, g _.41._,-._i_-.1-.-._4_. A *.'.-./fe..d...'9... J.- 4._ d _ l _. i ' i ! ! ' i,! i ' y k l L 4 ~ I d _1_ j._ _ _.-._L.._.4_4..._._4._... - _ _ ' l 4 l _g. o l -h 8 8 88 ,-n.i .e.-- l-m 1 ;! ! ! ;

i.,l o

P ~_m o ~ .a_;_._ a_ i _,i _ _., _l { _.s_,.. i - ,+1 i .. i i i i -.._ _' p_ . # w __ _+-- _+ 3 _4

i i ' ' ~ ~ ! i i
i

i : i a j _I.,_._ ._4_. i _4,______. ,.._ f. 4 _[__

.d_... _._- __.. R 2.

i . i 1 1 , s., ...._._4.__c_-_ _t_.- 4.__.,.__.~_._ e ,_+_1 .._4_._. 4.m.___e,_.#.-__ mam ' is T 4 t

i i,

I i 1 i 4 i i, i - i 4 - i i i f L. 1.._ 4 _.L,._J_ l _L._ p!. i_ L 4 '__4 4_ i _4 -.i 4 5 i 4., _.4 _.__m __1._ _L -4._?-,.'.__m- [ _..u__ y u

i

~ l ! i ! _ r: i ! ;

i

~ _.w,_t__l_ _,l y. i l : : i t au _i_._2_,_., 2u _m,_ _ ; v i _.1__-

i,. ! !.__ !. l

-___+._._~_,._a .,! __2 i

j ;

._.m I ,y W i i l ! y...,+._m._ __,m_f_,_ . _ __ f _.t.__+ _ ,l _.. i i _1..__4 y__.,i... + -4 ~. 1 .-._._._W X

1 ! 2 :3 ;4 ;s s 7 ;a u-.

_ + _ _ o ! tol 11 12113114 !ts lis ! 17l18 l 19 l20 ! 21! 22! 23l 24l 25l 26:27 !28 '29 ;30.31 :32 !33 i34 !35 '36 I37 l 38 [39 l40 j iy 0 = Debns & Sandsample

t. ; ummm ums w' W Figure 4 : Soil Survey Plan # 1 under Bldg. - 27 (EA-1) as of 05/09/98 S N

; i i

1.5 l 617 8 8

2 3 ;4 i

9 l 10 11 j12 !13 !14 !15 j16 l 17l18 ( 19 i20 ' 21l 22 23 j 24125! 26 j27 l28 :29 (30 '31 i32 l33 :34 !35 -36 37138 :39 [40 i i r I,,,,, 1 i e __#___.i1_J 1 i j p" i _4_ _.4 t 4 4_a a_. &_4 _ i _I 6 i - i ~ j I

' i i

j i '__4 +_ . i l } t t i i ! I i j ! ; ___._ l'.__.j I. } I 1 i ? 1 I i 1 ' + + 4.__+ _ _ __+_ ! - i, _ _ +. i -i I i i

+

6 A [__ _.._a' I i ! l i ; 1, i I i - < ' tA t i t._l t [_,e.4 .aner iemovaQ _a._ _.__L.a a_uB. i 4 B l

__um._ a i

I i ' i BLDG.'27 /EA;f) i < i Trencn hmed j i i i ! i t u : 2 ! l { l l, {_a t C j__,L,, ,j i j j j _,,}_. .,.,_3.___+ I L_J I i,j l i !.__I_,_ l j,,,,a _,1_,- ; i l ! ! } C _P i ' [__I._i_1 <._i ! i_ i. W__.LLj tl!.'I!! Lo 2 Ii! i l ! i E ' i ! ! ! ! l I ! s, i Mi! i 1 ' !

Qi l l E

F

}
l l iels4i

! : ssA * ' 's__7,!s! i _._L_ l 7"'l" sy, sis. 1 a_,.. __ _._ - _ n. ? + ; n_ y n s J _.-p4-+ll h, g _ -_ _.- G l l 1 % je,_ $ i 1 ss; I j l l ! l - a- -a _ s12 ! j st7 I i l ! i ss .L %ssa._g g m -!* H - H _ p _-+_ - 'G H I i i __ _ i 3q_p_4_;__ g ga,g_.;-4 9 - s Aet 9 _ s14;__.L L_ l 1 i I stalet_.7_2 =

i H;, '_Lm{ t-M+_ u_u ssat_ysis;; sis i: ' pH t

yg y l k +_7 v lI' I {Of"a%s_.J _ 1 g -1 I L L 7-4 .__2_ plL4 r r 4

. $i L M 4____ _;_

_p._4._ 1 _ 2__ _ L h K ' i l E 4 ;m i ! N I.l N N'i! ! ! I

i ' i i I

g I 3###### O A _i _ #_q '_ r._.a 3 i L i 50 ~ I~ ~ " _~ L_ p p o m $- f T : ! N 4_LJ-w

1. + 4 -- L M l l :

N tj [@r !. jg .i j g,. _.! _._,!__hil4._ 4_E

i. j i !

.! _.__ r{

y 1

1 l ! N 4 j j ss $2s h4 M I d j ,I J' l _l [3 O ! j ; ; Unaffected Area _ 2!I C L _-._' ~ __ +, M& ! ! ! l i es23.. .__4_.. 20 e ! I i O l m_2_.s _ P l i ; ! t .._._.,_s,_7,.

s s2s *p i i '

,._g g!_ _ _..m __ __a i i ! i i , _ j pa_.2 _. n _g__2-_2_ _+i__4 _ _,. s21 le!._{ g-L. _ p_ .2_ 2 L_4__ .._2 o : ! l 1 : ; _ m._ m'_,_,_ s29p! ; i i

i i

! s22p ! i t a R I ! ; i ! l i ; i i i 1 l t j aj + : L._ ;_. _+j 1 i i ! i i I +__4_ . l i a _ #..__p.._4 ._2 g c p._u__4.__1_ : i 4 '

4. _4. _.. L._2._.l.._w _ +, _

._wg S I' i l i t l i 5 ! l. _1_.L 4 _J._4.__4 I i - i ' ' j_ i _1 _4_ i._._.i._ J l _._1_.__ j t._.d_Q _4_ _j_ ' ' i i l i_ L+1_ _S T 4 . l l ' ___ 2 _,. _ _,i i l i 4 I i i ! ! > j _4_ l i i '4-__.._J__.b,,'_L+-

T~

..._. _. 4._ 4__4 o m_.4 i .._.4 _ g. _

._ p _.....__4 4_ _1_._. l._ 4.-

i_ __I._._1_._l._q _ I_. p _L _i.._ i, _ _d. _p._ _. __1_.. _. + U. v __3_ _3 __ +3 _.- _.: : 3 4 __+_._ m .__._._+__4_

,_._._1._...

_ _ +. _. - , y. W l

; '. ' i ;

l i. ! ! { :._w( _ + _ _4.. x _,. t_%%..

i i !

l j ! i t +_.,, 2- . _ - + _ c_..;____.___4 i ; i i ; i !

! ' ' ', ;w X

l1 2 i3 l4 ;s e i 7 i 8 i 9 ; to! 11112113 !i4 ;1s lts !17:1s lie i2a ! 21; 22l 23: 24! 2sl 2s!27 !28 :29 ;30 l31132 l33 l34 l3s ;3s :37 ! 38;39 l40 i -. ~ _. + - 7 'y imI O - Surface & subsurface sample ammN = Composite sample fivm bottom of the trench y = Core samples D<xxxxxxXI = Composite sample from side of the trench A = Side of trench (mid-trench) L-. 1 - Removalofconcrete (~ t foot wide) O = Grab sample O =Grabsampleunderconcrete

May 29,1998 3 L. Gonzales/ John Turner MG4mpbo -Y b-IM " Revised Final Trench Survey and Soil Sampline Plan #1 Addendum for Buildine 27 EA-1)" dated May 15.1998 Introduction The May 15,1998 Pian covers the radiological survey of the concrete lined trenches, soil sampling of the debris / sand inside the trenches and soil sampling under the excavated concrete. At that time it was assumed that the fill soil would be removed and disposed of as radioactive waste. However, the quantity of fill soil in the south end of the trench was larger than expected. The material at this location fills the trench completely. Therefore, additional sampling was performed to characterize this fill soil and determine if the material / pipes may remain "in place" without further remediation. In order to gain access to the drain pipes along the bottom of the trench (one of which lead to the hot drain line), 5 drums of soil was removed from ~ grids "11/12/13L". Items Comoleted (1) Twelve (12) debris / sand samples were taken of the " fill" material located in the south portion of the trench. Figure 1 shows the location and approximate depth of the samples. Each of the 12 samples was a surface sample (0-6") taken from the top of the fill material. One sample (#41) was taken at a depth of about 24" (where 5 drums of soil had been ) remrwed). Two samples (#42 and #43) were taken at a depth of about 32". Several of these samples were taken at - 32" below the surface of the " fill" material. All of these results (gamma spec) are at or below background levels, except for sample #42 taken at ~ 32" below the surface of the material). Samole #42 results: Cs-137 at [ 0.03 pCi/g

118.3%), and Co-60 (average of 1173/1332 kev peaks) at [0.10 pCi/g
63.0%].

(2) A sample of soil was collected from each of the five drums of fill soil removed, individual samples were obtained from each of five drums (55-gallon barrels) of" fill" material removed from the trench. This material was removed to expose a small surface of the concrete lined trench and the two pipes for radiological scanning and sampling. All sample results (gamma spec) were below background levels. Although one sample revealed Cs-137 at [0.02 pCi/g

71.2%].

(3) There are 2 remaining pipes in the trench under the fill soil (these pipes were removed up to this point). A sample of soil / debris was collected from the inside of each pipe. One from inside the pipe which lead to the hot drain line (west pipe) and one f om inside the pipe on the east side (not known to have ever contained radioactive materials). Both pipe sample results (gamma spec) exhibited " trace quantites" of radioactivity. I 2

3 West (right) pipe: U 235 at [ 0.37 pCi/g A 70.8%] -(144 kev peak), Cs-137 at [0.58 pCi/g

11.9%] and Co-60 (average of 1173/1332 kev peaks) at [0.17 pCi/g
30.0%].

East (left) pipe: Cs-137 at [0.42 pCi/g 17.9%] and Co-60 (1332 kev peak) at [0.04pCi/g

75.5%].

Although the values are well below the release criteria, it is not known if the levels decrease or increase further south. Complete removal of the pipe would require that a large quantity of soil (all found to be well below the release criteria) be removed. Instead of doing this, the following actions (as a result of the decisions made in the May 29,1998 am meeting) are being taken: " Fill" soil is being excavated, only at the far south end of the trench next to the south wall of the building, down to the pipes. As of May 29,1998, enough soil has been removed to demonstrate that the pipes extend out of the building. Samples at this location will be obtained from inside the pipes to see if the radioactivity decreases, increases or remains the same. (4) Survey the concrete lined trench in all areas where soil has been removed (same plan as the rest of the trench). If no contamination is present in areas next to the fill soil areas, then the soil does not have to be removedfor this reason. ) (5) Obtain drawings from facilities or J. Greenwood showing where these lines extend outside of Building 27. ) W:\\D-PLAN \\EAl-ADDI.598 3

i,I llll lI)j !i \\\\ lJ NY-w . S tyNop oqg T u v qy ABqqE p qH J y ) 4, 0 04 9 9 3 e l 3 8 8 3 3 m 7 7 '3 p m 6 6 !3 3 m 5 5 3 3 m '4 4 3 3 a 0 3 3 3 2 s ll l 2 3 3 m 1 1 3 3 ) 1 m 0 0 3 A 3 E 9 a ( 9 2 7 i 2 2 ll 2 G n 6 28 D e 7 7 2 L 2 B m 6 6 2 2 5 5 2 a i 2 i {I s 4 4 2 2 a 3 3 2 2 6 l m m l$ 2 L 2 2 e A 2 V l' ly ml5lIll jN 9 1 1 / 2 s E 2 1 D w 0 D m 'N 2 I 0 / S 2 f lp a o 9 9 t 1 s f A ) I1 ih _f 8 8 1 1 7 n g 7 A a 1 1 E m o ( 6 t jI e _o 1 o 7 5 ss 5 2 1 y 1 -a.W_2 s r . o 4 t 1 g 4 d s i 3 2 B lj s - g II 13 1 r 2 j mj 2 o 1 f p l 1 j g a n 1 g 1 1 r a 1 lP o IQhd 0 t L y 1 e 9 v 9 r u S 8 a e d J e n 7 p 7 a ro ~ s lI i s S 6 =e s / w n E b 5 5 e D 4 e i 4 h p m c 3 m1 3 a n e s i r 2 2 m T a s 1 22 1 e a r s i ug m o L O A B C D E F G H J l M N O P Q R S T u v W X l l1l}}

ML20155K422

Text

Background

SUMMARY

5.0 REFERENCES

Navigation menu

Search