Text

Request to Release a Certain Portion of General Atomics Site of Unrestricted Use and Delete It from License: Namely, Tff Utility Corridor
	ML010720048
Person / Time
Site:	07000734
Issue date:	02/23/2001
From:	Asmussen K; General Atomics
To:	Adams M; NRC/NMSS/FCSS
References
	-RFPFR, 696/CAL- 3334
	Download: ML010720048 (73)
	v • d • e

{{#Wiki_filter:+ GENERAL&ATOMICS February 23, 2001 696/CAL-3334 VIA EXPRESS MAIL SERVICE Ms. Mary Adams Licensing Section 1/Licensing Branch Division of Fuel Cycle Safety and Safeguards, NMSS U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Docket No. 70-734; SNM-696: Request to Release a Certain Portion of General Atomics' Site to Unrestricted Use and Delete it From License: Namely, TFF Utility Corridor and ATTN: Mr. David Wesley (in Duplicate) State of California Department of Health Services Radiologic Health Branch Mail Stop 178 601 North 7th Street Sacramento, CA 95814-0208

Subject:

Radioactive Materials License No. 0145-37: Request to Release a Certain Portion of General Atomics' Site to Unrestricted Use and Delete it From License: Namely, TFF Utility Corridor

Dear Ms. Adams and Mr. Wesley:

As you are aware, General Atomics (GA) is continuing its efforts to decontaminate, as appropriate, and obtain the release to unrestricted use of selected facilities and portions of its site. GA has recently completed the Final Radiological Survey of a parcel of open land through which all utilities needed by Building 22 will be routed. Building 22 was the former TRIGA Fuel Fabrication (TFF) Facility. This parcel of land is called the "TFF Utility Corridor" and is located on General Atomics' Main Site as shown in the attached Figure

1. The total land area to be released to unrestricted use is - 67,000 ft2 (-6,200 m2 or -1.5 acres). No contamination was found in this land area.

The TFF Utility Corridor land area is bounded on the west by the "Linac Land Area." (See attached Figure 2.) It is bounded on the south by a portion of previously released land ("Torrey Pines Central"), parking lots, and the "soil staging area." Along the north it is bounded by previously released land areas associated with GA's Buildings 27 (radiochemistry) and 23 (the "Hot Cell Site"); and parking areas associated with Buildings 27 and 21 (TRIGA reactors building). To the east it is bounded by the "Torrey Pines Northeast" Land Area, which is pending release. 3550 GENERAL ATOMICS COURT, SAN DIEGO, CA 92121-1194 PO BOX 85608, SAN DIEGO, CA 92186-5608 (619) 455-3000

Mary Adams, NRCI David Wesley, State February 23, 2001 696/CAL-3334 Page 2 GA has documented the results of its radiological measurements and soil sampling and analysis for this land area in the enclosed report titled: "General Atomics' Final Radiological Survey Report for the TFF Utility Corridor," dated February 2001. The results documented in this report demonstrate that this area meets the criteria for release to unrestricted use as approved by both the U.S. Nuclear Regulatory Commission (NRC) and the State of California DOHS Radiologic Health Branch (State). Accordingly, GA hereby requests that both the NRC and State release the "TFF Utility Corridor" land area, as described in the enclosed report, to unrestricted use and delete it from GA's NRC and State special nuclear and radioactive material licenses, respectively. The history of use of facilities and land areas near and adjacent to the TFF Utility Corridor involves both NRC and State licensed materials. However, the most likely sources of contaminaton - though GA found none - would have been the nearby TRIGA Fuel Fabrication Facility or the Hot Cell Facility, both of which the NRC had the lead regulatory oversight role. Therefore, it follows that it is appropriate for the NRC to take the lead in coordinating this release; including regulatory agency confirmatory surveys, as deemed appropriate. If you should have any questions regarding this information, please contact Laura Q. Gonzales at (858) 455-2758, or me at (858) 455-2823. Your assistance in responding to our request is very much appreciated. Very truly yours, Keith E. Asmussen, Ph.D., Director Licensing, Safety and Nuclear Compliance Attachments: Figure 1: "Main Site and Sorrento Valley Site" (showing relative location of TFF Utility Corridor) Figure 2: "TFF Utility Corridor Relationship With Other Facilities/Sites"

Enclosure:

Report titled: "General Atomics' Final Radiological Survey Report for the TFF Utility Corridor," dated February 2001. cc: Dr. D. Blair Spitzberg, Chief, NMSS Branch 3, Region IV Mr. Wayne L. Britz, Fuel Cycle Inspector, NRC Region IV Mr. Emilio Garcia, Fuel Cycle Inspector, NRC Region IV Ms. Kathleen Henner, State of CA, Brea, CA Dr. Ronald Rogus, State of CA, Sacramento, CA

Figure 1: Main Site and Sorrento Valley Site Building Numbers Names Bsilding 1 Admrinitration rN Building 2 Science Laboratories A, B, C.

7.

Building 7 Cafeteria -4 Sw +E Building 9 Experimental Building Building 10 Maintenance Building Building 13 Technical Office Building S Building 14 Technical Office East Building 15 Technical Office East Building 19 Swimming Pool Building Building 21 TRIGA Building Building 22 TRIGA Fuel Lab Building Building 23 Hot Cell 3 Building 25 Waste Yard Building I Building 27 Experimental Area Building 27-7 Experimental Area I IINDUSTRY Building 29 Experimental Area Building 29-2 Emergency Vehicle Storage Building I 6 Building 30 LINAC Complex 37 Building 31 TRIGA Storage Building Building 31-1 Neutron Radiography Building 4 Building 31-2 ECF Critical Building 1 Building 31-3 Storage Building St Building 33 Fusion Building .INHILL ST Building 33-1 Fusion Lab Building Building 33-5 Fusion Building Annex 5 Building 34 Fusion Doublet Ill Building Building 34-1 Fusion Doublet III Capacitor Building Building 34-2 Fusion Doublet III Lab Building Building 34-3 Fusion Doublet III Storage Building 34 34-1 Building 35 Test Tower Building Building 35-1 Facilities (Shipping & Receiving) Building Building 36 Blower Assembly Building Building 37 Sorrento Valley Building Building 39 Sorrento Valley Building B u ild in g 3 9 -1 S to ra g e B u ild in g L O T 3 2 "E Building 41 Raw Slock Facility Building 42 NDT Facility Building 45 Helium Circulator Test Facility SITE Building 63 3550 Dunhill St. Building 64 11030 Roselle St.// Building 65 11040 Roselle St. Building 66 3520 Dunhill St. OPEN SPACE Building 66 3510 Dunhill St. CONTROLLED MAIN SITE x **31-1 LOTS 3/1-3 j 122 302 TFF Utility Corridor SINDUSTRY J -25

0)

SGENERAL LOTS Q. ATOMICS LOT 31 cc, COURT C7 SINDUSTRY N9 I- -~ 001 UCSD 00 33-5 LOTS -FENCING PROPERTY LINE 0 250 500 750 1000 SCALE IN FEET

Figure 2: TFF Utility Corridor Relationship With Other Facilities/Sites N S Former E: Hot Cell Site

2' A

A A A A" A/ 'A/ Open Land Area 44 I ............... S....................... AJ A A A 4, / Soil Staging Area 1V/ cm = 15m = -50' i r"

GENERAL ATOMICS FINAL RADIOLOGICAL SURVEY REPORT for the TFF Utility Corridor Prepared By: William LaBonte and Laura Gonzales Illustrated By: Steve Finchurn Final Survey Technicians: Mike Dupray and Barbara Hunter Confirmatory Survey Technician: Joe Sullivan February 2001

Table of Contents IN T R O D U C T IO N................................................................ I SITE D ESC R IPTIO N............................................................. I PREVIOUS ACTIVITIES (HISTORY OF USE) & CLASSIFICATION 2 CRITERIA FOR RELEASE TO UNRESTRICTED USE................................. 4 Release Criteria for Asphalt and Concrete Surfaces 4 R elease C riteria for Soils..................................................... 4 Exposure R ate G uideline..................................................... 5 INSTRUMENTATION & BACKGROUND MEASUREMENTS........................... 5 Background Measurements for Instruments/Detectors 5 Background Soil Concentrations of Concern..................................... 6 Exposure Rate Background................................................... 6 FINAL SURVEYS PERFORMED................................................. 6 O bjectives and Responsibilities............................................... 6 S urvey P lans.................. ..... 7 TFF Utility Corridor Open Land Area.......................................... 7 Soil Sampling......................................................... 7 SU R V EY SU M M A R Y............................................................ 8 RESULTS OF THE OPEN LAND AREA FINAL SURVEYS........................... 9

Scanning, 9

Fixed Exposure Rate M easurements 9 Fixed M easurements (a and 3)............................................... 9 Rem ovable Activity.................................................. ...... 9 So il S am ples.............................................................. 9 CONFIRM ATORY SURVEY...................................................... 10 C O N C L U SIO N................................................................. 10 List of Tables (unpaged) Table I USNRC's Acceptable Surface Contamination Levels......................... T-1 Table 2: State of California's Acceptable Surface Contamination Levels................. T-2 Table 3: Building 22 (TFF) Utility Corridor List of Instruments....................... T-3 Table 4: TFF Utility Corridor Swipe Survey Results................................. T-6 Table 5: TFF Utility Corridor Soil Sample Results.................................. T-8 Table 6 Background Soil Sample Results........................................ T-23 i

List of Figures (unpaged) Main Site and Sorrento Valley Site Relationship Between Building 27-1, 27, 21,23 and 22 Tff Utility Corridor Classification TFF Utility Corridor Grid Map TFF Utility Corridor Fixed Alpha Measurement Locations and Results TFF Utility Corridor Alpha Scan Survey Results TFF Utility Corridor Fixed Beta Measurement Locations and Results TFF Utility Corridor Beta Scan Survey Results TFF Utility Corridor Exposure Rate Measurement Locations and Results in p.R/hr at 1 Meter from the Surface TFF Utility Corridor Swipe Survey Locations TFF Utility Corridor Soil Sample Locations TFF Utility Corridor Soil Sample Locations, Area I TFF Utility Corridor Soil Locations. Area 2 TFF Utility Corridor Soil Sample locations, Area 3 Appendixes Appendix A: Final Survey Plan for the TFF Utility Corridor Appendix B: TFF Utility Corridor Confirmatory Survey ii Figure 1: Figure 2: Figure 3: Figure 4: Figure 5: Figure 6: Figure 7: Figure 8: Figure 9: Figure 10: Figure 11: Figure 1 Ia: Figure I I b: Figure I I c:

+GENERAL ATOMIcs Final Radiological Survey Report For Building 22 Utility Corridor Introduction General Atomics (GA) is continuing its efforts to decontaminate, as appropriate, and obtain the release to unrestricted use of selected facilities and portions of its site. GA has recently completed the Final Radiological Survey of a parcel of open land through which all utilities needed by Building 22 will be routed. This parcel of land is called the "TFF Utility Corridor" and is located on General Atomic's Main Site as shown on Figure 1. The total land area to be released to unrestricted use is - 67,0000 ft2 (- 6,200 m or - 1.5 acres). No contamination was found in this land area. GA is requesting both the Nuclear Regulatory Commission (NRC) and the State of California (DOHS/RHB) release this parcel of land to unrestricted use. Building 22, Building 27 and the former Hot Cell Site (which previously included Building 23), all adjacent to this land area, have already been released to unrestricted use. This report documents the results of the radiological measurements and soil sampling and analysis completed on the -TFF Utility Corridor". These results demonstrate that this area meets the approved criteria for release to unrestricted use. Site Description The TFF Utility Corridor land area is bounded on the west by the "LINAC Land Area." (See Figure 2.). It is bounded on the south by a portion of previously released land (Torrey Pines Central ), parking lots, and GA's "soil staging area". Along the north it is bounded by previously released land areas associated with GA's Buildings 27 (radiochemistry) and 23 (the "Hot Cell Site"): and parking areas associated with Buildings 27 and 21 (TRIGA reactors building). To the east it is bounded by the Torrey Pines Northeast Land Area, which is pending release. The TFF Utility Corridor land area was originally called the "TFF Service Corridor" but was changed to "TFF Utility Corridor" to eliminate the confusion that might be created due to the "Building 2 Service Corridor" which was being surveyed at the same time. Some of the documents and surveys contained in this report which refer to the TFF Utility Corridor are titled TFF Service Corridor. The footprint of the TRIGA Administrative trailer and a portion of the land directly adjacent to the TRIGA facility is excluded from this report. I of I0

+ GENERAL ATOMICS Final Radiological Survey Report For Building 22 Utility Corridor Previous Activities (History of Use) & Classification Those portions of the TFF Utility Corridor which are within what were previously established as Controlled Areas for Buildings 21, 22, 27, and the former Hot Cell Site are classified as "Non Suspect Affected Areas" due to their proximity to these facilities. The land areas outside of the Controlled Areas are classified as "Unaffected Areas". See Figure 3. The TFF Utility Corridor itself was not used for any activities involving the use of radioactive materials. The following descriptions are of activities that were conducted nea this land area. Buildingý 21 Building 21 Contains three (3) TRIGA Research Reactors which were constructed between 1958 and 1966. These small non-power reactors were utilized in both industrial and academic applications for training, research, and isotope production. The Mark III reactor was De-fueled and decommissioned approximately 20 years ago and is awaiting final surveys for release for unrestricted use. The Mark I and Mark F reactors have had their NRC licenses amended to authorize Possession Only and are currently undergoing decommissioning. Building 22 Building 22 was the TRIGA Fuel Fabrication Facility which was constructed in 1974 to manufacture TRIGA" non-power reactor fuel elements. The physical form of uranium handled or stored in the northern portion of Building 22 and the vault was predominately metal and included uranium metal and uranium-zirconium alloy metal such as U/Zr and Er(U, Zr)H, 6. Small amounts of uranium oxide compounds (UO 2 and U30 8) were also used in the building. During D&D, residual contamination was found in the Furnace, Machine Shop and Hydride areas of Building 22 (main production area), due to the handling and usage of special nuclear materials (i.e., enriched uranium). This residual radioactive contamination was limited to virgin enriched uranium. In the southern-most end of the building, no fuel manufacturing operations were performed, however, work involving limited and short duration use of special nuclear material (enriched uranium) was authorized. D&D activities were completed in 1998. Final surveys and confirmatory surveys were completed and the Building was released for unrestricted use by the NRC on May 14, 1999 by amendment No. 55 of License SNM-696 and the State of California on September 1 0. 1999 by amendment No. 140 to License # 0145-37(80). 2ot 10

.GENERAL ATOMIC$ Final Radiological Survey Report For Building 22 Utility Corridor Building27 Building 27, EA-I ( Radio-Chemistry Laboratory), was constructed in 1965. This building contained Radio-Chemistry laboratories and Analysis equipment in support of GA's numerous Nuclear related activities. Operations in this building ceased in September 1996. Decommissioning activities were completed in 1998. The GA final survey of the Building was completed in November, 1998. The State of California released the Building for unrestricted use on May 6, 1999 by amendment No. 139 to Radioactive Material license #0145-37(80) and by the USNRC on May 14, 1999 by amendment No.54 to License SNM-696. A final survey on the land located to the West, South and Southeast of Building 27 was completed by GA in January, 2000. This land area was released for unrestricted use by the State of California on June 27, 2000 by amendment No. 142 to Radioactive Material License # 0145 37(80), and by the USNRC on September 18, 2000 by amendment No. 67 to license SNM-696. The Former Hot Cell Site Built in 1958 as a heavily shielded remote-handling laboratory, the Hot Cell Facility (HCF) supported a wide variety of radiological and investigative operations. The HCF contained three shielded cells, the High Level Cell (HLC), the Low Level Cell (LLC), and the Metallography Cell. The HLC was used to perform destructive post-irradiation examinations on fuels and structural materials and instrumentation for dosimetry. The HCF yard and the service gallery had been used for cask handling and cask maintenance activities, and for waste consolidation, packaging, and characterization (e.g., weighing, gamma scanning). During Decommissioning activities, the HCF was completely dismantled. A substantial portion of the building was disposed of as radioactive waste, including the Cells Manipulator Repair room and Machine shop. All support equipment associated with the HCF, such as underground tanks, wells, and piping systems were excavated and disposed of as appropriate. Final surveys on the Hot Cell Site land areas were completed by GA in January 2000. The predominate isotope encountered was Cs-137. and on occasion. Co-60 and Cs-134. Following confirmatory surveys performed by the NRC and ORISE. the NRC released the Hot Cell Site by SNM - 696 License Amendment No. 66 dated July 3, 2000. The State of California released the Hot Cell Site to unrestricted use by License 0145-37 Amendment No. 143 dated August 31, 2000. 3 of 10

GENERAL ATOMICS Final Radiological Survey Report For Building 22 Utility Corridor LINAC Land Area Final Surveys for Linac and Linac North land areas are currently in progress. Soil Staging Area The temporary Soil Staging Area, located at the East-Southeast boundary of this land area, was established in November, 1998 to temporarily store D&D materials (mainly soil), surveyed and released by GA but waiting release to unconditional use/disposal by the appropriate regulatory agency. During the D&D operations at the Hot Cell Site, some contaminated soil (approximately 40,000 ftW) was placed in this area (and segregated from other materials). This soil, along with ".clean" D&D material from other projects, is currently stored in this area. Criteria for Release to Unrestricted Use Release Criteria for Asphalt and Concrete Surfaces The primary isotopes of concern for this area are 20% enriched uranium (234U and 235U) which was used at building 22 (TRIGA Fuel Fabrication Facility) and fission/activation products (' 37Cs / 6"Co) from the former Hot Cell Site. TRIGA Reactor Facility (Building 21), and Radio Chemistry (Building 27). The applicable NRC guidelines for enriched uranium and beta/gamma emitters (including Cs-137 and/or CO-60) are as follows: 5,000 dpm/100 cm2. averaged over a I m2 area 15,000 dpm/1l00 cm-, maximum in a 100 cm' area if the average over I m2 is met 1,000 dpm/100cm2, removable activity Release Criteria for Soils The predominant radionuclides found in the soil at GA and the approved release criteria in pCi/g (above natural background concentrations) for these radionuclides are provided as follows: Enriched Uranium (U-234 + U-235) 30 pCi/g Thorium (Th-228 + Th-232) 10 pCi/g Depleted Uranium 35 pCi/g Cs-137 15 pCi/g Co-60 8 pCi/g If more than one radionuclide exists. the sum of the fractions of the concentrations is calculated as follows: 4 of 10

4 GENERAL ATOMICS Final Radiological Survey Report For Building 22 Utility Corridor ci -C=<I Ci = The average concentration of radionuclide i in the sample above background levels. Li = The release criteria for radionuclides i. The sum of the fractions must be less than or equal to one (1). Exposure Rate Guideline Exposure rates measured at I m above the surface are not to exceed 10 pR/hr above natural background levels. Instrumentation & Background Measurements A list of instruments used during the radiological surveys is shown in Table 3. The table includes: (1) a description of the instrument, model number and its serial number, (2) a description of the detector (if applicable) and its serial number, (3) instrument ranges, (4) calibration due dates, (5) typical background readings and (6) calibration efficiencies (if applicable). All of the instruments used were calibrated semiannually and after repair, except for exposure rate meters which were calibrated quarterly. Background Measurements for Instruments/Detectors Building 13 on GA's main site was used for conducting background measurements with instruments used for the final survey because: ( I ) there is no history involving radioactive materials or storage of radioactive materials in Building 13, and (2) the various surfaces and construction materials found at the Hot Cell Site could also be found within and outside of Building 13. Background information, where appropriate, is included in Table 3. Minimum detectable activities (MDA's) for instruments used for fixed measurements, for each type of surface (see Table 3). were calculated using equation (5-2) from the NUREG/CR-5849 as shown below: Equation (5-2) MDA-= 2.71 +4.65 (dpm/lOOcm2) txEx A 100 5 of 10

4 GENERAL ATOMICS Final Radiological Survey Report For Building 22 Utility Corridor Where: BR = background rate (cpm) t = count time (min) E = efficiency A = area of the detector (cm 2) Note: MDA information, when applicable, is provided in Table 3. Background Soil Concentrations of Concern Typical background concentrations measured by gamma spectroscopy in soil near the GA site have been established (at the 95% confidence level) and are provided in Table 6 along with the locations where these samples were taken. Exposure Rate Background Typical exposure rate background for this site using a Ludlum Model 19 micro R meter is about 15 pR/hr measured at 1 m from the surface of soil. This value can be measured south of Building 15 (an office building on the eastern portion of the GA site). Measurements taken offsite in 10 different locations (9 offsite and I onsite at a non-impacted area near Building 15) over a period of 15 months also averaged - 15 iiR/hr (measured at I m from the surface). The range of 12-18 pR/hr is typical at the GA site for the external dose rates measured at I meter from the surface. Background over asphalt is higher due to the high concentrations of naturally occurring radioactive material (NORM). This background fluctuates dependant upon the asphalt batch used and the date applied. This background is routinely less than 30 [LR/hr at approximately I from the surface of the asphalt. Final Surveys Performed Obiectives and Responsibilities The objectives of the final survey plans were: ( I ) to demonstrate that the average surface contamination levels for each survey unit were within the approved release criteria, (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 2, (3) that a reasonable effort was made to clean removable contamination and fixed contamination, (4) that the exposure rates are less than 10 [tR/hr above background measured at I meter above the surface, and (5) that the soil concentrations were below the approved soil release criteria. 6 of 10

+ GENERAL ATOMICS Final Radiological Survey Report For Building 22 Utility Corridor Surveys were taken in accordance with an approved survey plan by qualified Health Physics Technicians having a minimum of three years health physics experience. Soil samples were counted in GA's Health Physics Laboratory which maintains an effective QA program. Every survey taken was documented on a daily basis to a worksheet/drawing showing the approximate locations surveyed/sampled. The documentation included the results of the measurements (including units), the technician's signature, date. instrument(s) used (including the model and serial number of both the ratemeter and detector). calibration due date, % efficiency, background readings (if applicable) and any other pertinent information. Each soil sample collected was properly logged, sealed, labeled, packaged and tracked. The sampling locations were documented on a drawing. Survey Plans Final Survey Plans were developed based on the previous history of the adjacent Buildings. and the Torrey Pines Northeast land area site, the radionuclides of concern for this area, the potential for contamination, the various types of surfaces encountered and the classification of the area (Non-suspect Affected). See Appendix A for Final Survey Plans for the TFF Utility Corridor. TFF Utility Corridor Open Land Area The entire open land area was "gridded" into 2 m x 2 m grids. The surface area was gridded in order to: (1) facilitate systematic selection of radiological measuring and soil sampling locations, (2) provide a means for referencing a measurement back to a specific location and (3) establish a uniform and distinct identification system. The one axis of the gridwork was delineated by numerical characters and the other axis by alphabetical characters. This established unique grids of easily identifiable entities. See Figure 4. Soil Sampling Soil samples were taken where soil was exposed as indicated in Figures 11, 11 A, I IB, and I IC, TFF Utility Corridor Soil Sample Locations. Each of the soil samples taken was approximately I kilogram in mass. The samples were properly logged, labeled, tracked and packaged into plastic bags. All debris (i.e., grass, rocks, sticks, asphalt and foreign objects) was removed from each sample. Each soil sample was individually crushed to reduce large lumps, dried, placed into a tared marinelli beaker (filled to the top), weighed. sealed and transported to GA's Health Physics Laboratory. 7 of 10

4+ GENERAL ATOMICS Final Radiological Survey Report For Building 22 Utility Corridor Soil 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. Soil samples were counted for a minimum of 30 minutes each. A 30 minute count was sufficient to detect the radionuclides of concern at levels well below GA's approved soil release criteria. Survey Summary Comparisons of the Site Decommissioning Plan requirements with the Final Surveys performed in relation to the percentage of surface area scanned, number of measurements (i.e., number of fixed radiation measurements). exposure rate measurements (P R/hr) and soil samples taken are provided as follows: The total surface area to be released is approximately 67.000 ft' (-6,200 im 8 of 10 Comparisons of Site Decommissioning Plan Requirements with Final Surveys Performed on the TFF Utility Corridor Open Land Areas Survey Gridding

of Direct
of Exposure Surface Scans
of Soil Measurements Rate Samples Fixed a, P3, or Measurements Taken and swipes (pR/hr)

Analyzed GA Site Not 30 minimum I per 10 m or I 10% of surface Not Decommissioning Required I per 50 m2 or I per - 3 m areas (asphalt and Required Plan every - 7 m total-320 concrete) Unaffected Area readings Final Surveys

Yes, Fixed ca =36, 1 per 10 m-or 1 100% of accessible 50 surface Unaffected Area 2m x 2m Fixed P =53, per - 3 m concrete and (0-6")

Swipes=50 Total = - 800 asphalt surfaces samples Total = 139 readings GA Site Not 30 minimum I per 10 m2 or I 10% of Surface Not Decommissioning Required 1 per 50 m-2 or I per - 3 m Areas (asphalt and Required Plan every - 7 m Total z 300 concrete) Non-Suspect Affected Area Final Surveys Yes. Fixed cX =36. I per 10 m2 or I 100% of accessible 163 surface Non-Suspect 2m x 2m Fixed P3 =35. per - 3 m concrete and (0-6") Affected Areas Swipes=37 Total=- 730 asphalt surfaces samples Total = t08

GENERAL ATOMICS Final Radiological Survey Report For Building 22 Utility Corridor Results of the Open Land Area Final Surveys The results for the Open Land Area Final Surveys are provided in figures and tables indicated below for each survey technique. Scanning 100% of the accessible asphalt and concrete surfaces werescanned with a, and P3, detectors. There were no detectable activity levels above pre-established alert levels. The results of these surveys are presented in Figures 6 (for cc) and 8 (for (3). Fixed Exposure Rate Measurements Direct radiation levels were measured at I m from the surface at - 1530 locations using a 2"x2" NaI(TI) detector. Maximum readings were <25 pRPhr, which is less than 10 [R/hr above background. Thus. all readings were less than the approved release criteria. See Figure 9 for locations and results. Fixed Measurements (t and (3) There were 73 fixed a and 88 fixed P3. measurements taken. All results were far below the release criteria. See Figures 5 for a, and 7 for P3, locations and results. Removable Activity A total of 87 swipe measurements were taken and analyzed for a and P3 activity. The highest a activity was <10 dpm/100 cmM, the highest P3 activity was 10 dpm/100 cm2. These results are far below the approved release criteria. See Table 4 for results and Figure 10 for sample locations. Soil Samples A total of 213 soil samples were collected from the exposed ground areas. The approximate soil sample locations are shown in Figure I I. I IA, II B, and I C. Gamma spectroscopy results are provided for these samples in Table 5. The isotopic results (pCi/g) indicated that, in some samples, 238U, 235U, 137Cs, and 60Co was present above natural background levels, but the results were all well below the approved soil release criteria as summarized below. 9 of 10

.GENERAL ATOMIcS Final Radiological Survey Report For Building 22 Utility Corridor 2U in p 35U in PiL 137CS iCo in High 3.16 +/- 1.50 0.69 +/- 0.42 1.76 +/- 0.87 0.29 +/- 0.10 Low ND ND ND ND Average 1.31 +/- 0.89 0.14 +/- 0.09 0.15 +/- 0.07 0.02 +/- 0.02 Nominal 2.26 0.18 0.09 ND

Background

Note: ND means not detected. The High concentrations for each isotope did not occur in the same sample. No sample had a sum of fractions greater than 1.0. Confirmatory Survey Following the completion of the Final Survey, a Confirmatory Survey was performed, by a GA HP technician that was not associated with the Final Survey, in accordance with an approved survey plan. This survey consisted of 17 surface soil samples, 22 fixed a measurements, 31 fixed [3 measurements, 25 swipe surveys (analyzed for a and P3 activity), and dose rate measurements at 38 locations taken I meter from the surface. All measurements were in agreement with the final survey results, which is: no contamination was found in this land area. See Appendix B for details. Conclusion Final contamination and radiation surveys, as well as the results of analyses of soil samples, as documented in this report, demonstrate that the TFF Utility Corridor meets the NRC and State approved criteria for release to unrestricted use. 10of 10

Table 1: USNRC'S ACCEPTABLE SURFACE CONTAMINATION LEVELS Nucides Average-Maximum"-r Removableh" (dpm/100cm2 ) (dpmn/l00 cm2 ) (dpm/100cm2 ) U-nat, 23*U, 28U, & associated decay products 5,000 L 15,000 a 1,000 a Transuranics, 226Ra,* '2 Ra, 23°Th, 228Th, 231 Pa, 100 300 20 227Ac, 1251, 1291 Th-nat, 2 -'Th, 9"Sr, 2 -'Ra, 2 4 Ra, 32U, 126I I 1,000 3,000 200 1311 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. a Where surface contamination by both alpha-and beta/gamma-emitting nuclides exists, the limits established for alpha-and beta/gamma-emitting nuclides should apply independently. b As used in this table dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background. efficiency, an geometric factors associated with the instrumentation. c Measurements of average contaminant should not be averaged over more than I square meter. For objects of less surface area. the average should be derived for each such object. d The maximum contamination level applies to an area of not more than 100 cm 2. e The amount of removable radioactive material per 100 cm 'of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped. f The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mRad/hr at 1 cm' and 1.0 mRad/hr at I cm 2, respectively, measured through not more than 7 milligrams per square centimeter of total absorber. T-1

Table 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclides' Average"hs Maximumn'"A. Removable'"s _dpm/i OOcm) (ddpm/1OOcm-I) (dpm/100cm 2 U-nat. >SU. 2"U. & associated decay 5,000 15,000 1,000 products Transuranics. :>Ra. 22 Ra, 2 "Th, -*Th, 100 300 20 2'Pa. 2Ac, 121, 1"1 Th-nat. 232Th. "'Sr. ' 2 Ra. 24Ra,- I-U, "l. 1,000 3.000 200 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 a Where surface contamination by both alpha-and beta/gamma-emitting nuclides exists, the limits established for alpha-and beta/gamma-emitting nuclides should apply independently. b As used in this table dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background. efficiency. an geometric factors associated with the instrumentation. c Measurements of average contaminant should not be averaged over more than I square meter. For objects of less surface area. the average should be derived for each such object. d The maximum contamination level applies to an area of not more than 100 cm 2. e The amount of removable radioactive material per 100 cm2 of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects of less surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped. f The average and maximum radiation levels associated with surface contamination resulting from beta gamma emitters should not exceed 0.2 mrad/hr at 1 cm' and 1.0 mrad/hr at I cm 2. respectively, measured through not more than 7 milligrams per square centimeter of total absorber. Guidelines For Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses For byproduct. Source, or Special Nuclear Material, also known as "'Decon-I" incorporated into GA's State of CA Radioactive Materials License. T-2

'fable 3: TFF Utility Corridor List of Instruments Meter Detector Detector Calibration Efficiency Range lBackground D)escription S/N S/N Due Date (cpm) Average (Cl)hi) I.udlum Rate Ludlunm 1/24/00 21.70c7, with a Four Linear 1478 to 1765 The instrument is a gas-flow proportional Meter Model Sr-90 source, Ranges 0-on concrete, counter with an active probe area of 434 cm 2. Model 2221 43-37 S/N 086215 47c 500,000 & One 2161 to 2530 The detector and rate meter are combined and S/N 434 cm' Log 50-500,000 on asphalt mounted on a roll around cart. Thc instrument 86302 Beta features a static-flow system, quick connects, a portable gas bottle and a means to adjust the height of the detector from ground surface Ir optimum performance. ILudhum Ratc Idl1udhm 04/09/1) 22.72% Four Linear 1567-17 19 cpm The instrument is a gas-flow proportional Meter Model S/N 149017 06/14/01 22.74/c Ranges 0-on concrete. counter with an active probe area of 434 cm2. Model 2221 43-37 with a 500,000 & One 2175-2461) cpm The detector and rate tneter are combined and S/N 434 cnr Sr-90 source, I.og 50-500,000 on asphalt mounted on a roll around cart. The instrument 154202 Beta 47T features a static-flow system, quick connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance. I.udlumn Rate lIudlum SIN 147966 07/19/00 21.3097 Four Linear 0-26 cpm on The instrument is a gas-flow proportional Meter Model 12/27/00 21.30% Ranges 0-concrete. 0-32 counter with an active probe area of 434 cm-. Model 2221 43-37 12/28/00 21.30% 500,000 & One cpm on asphalt The detector and rate meter are combined and S/N 434 cm" with a Th-230 Log 50-500,000 mounted on a roll around cart. The instrument 148445 Alpha

source, features a static-flow system, quick connects, a 4Tu portable gas bottle and a means to adjust the height of the detector from the floor for optimuml__

_t performance. T-3

Table 3: TFF Utility Corridor List of Instruments Meter Detector Detector Calibration Efficiency Range

Background

Description S/N S/N Due Date (cpnu) Average (cpI) I.ud1lUn Rate Ludluni 08/25/00 20.26% Four Linear 2145-2274 cpm The instrument is a gas-flow proportional Meter Model S/N 094119 01/04/01 20.26% Ranges 0-n asphalt counter with an active probe area of 434 cm 2. Model 2221 43-37 01/10/01 20.020/ 500,000 & One The detector and rate meter are combined and S/N 434 cm 2 with a Sr-90 Log 50-500,000 mounted on a roll around cart. The instrument 97817 Beta

source, features a static-flow system, quick connects, a 471 portable gas bottle and a means to adjust the height of the detector from the floor for optimum perlormance.

I odlum Rate Ludlum SIN 083293 01110/01 20.49% Four Linear 2562-2704 cpni The instrument is a gas-flow proportional leter Model 01/I 8/01 20.49% Ranges 0-on asphalt counter with an active probe area of 434 cm 2. Model 2221 43-37 with a Sr-90 500,000 & One The detector and rate meter are combined and SIN 434 cm2

source, Log 50-500,000 mounted on a roll around cart. The instrument 97265 Beta 47T features a static-flow system, quick connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.

l.udlun) Rate Ludlum 02/06/01 26.20% Four Linear 1330+/-141 This instrument is a gas flow proportional Meter Model S/N 119444 02/20/01 24.14% Ranges C/2mins. counter with an active probe area of 100 cmr2 Model 2221 43-68 04/24/01 24.13% 0-500,000 & MDA=171 used primarily for beta fixed measurements. SIN 100 cm12 04/18/01 24.13% One Log dpm/ 100 cm 2. 84423 Beta with a 50-500,000 Sr-90 source, 47T l.ud1ltm Ludluin 10/12/00 21.58% Four Ranges 0-0-20 cpm on Alpha scintillator with an active probe area of Model-12 Model 43-65 S/N with a Th-230 500,000 concrete or 50 cm 2 used for Alpha fixed measurements -7 Alpha 094053

source, asphalt, 1Osec count and 20 cpm maximum background.

S/N 91051 Scintillator 4n MDA=768 ZiiS(Ag) dpm/100 cm 2 T-4

Table 3: '[FF Utility Corridor List of Instruments Meter Detcctor Detector Calibration Efficiency Range

Background

D)escription S/N S/N Due Date (cpm) Average Ludlunm Ludlum S/N 02/8/00 NA Four Ranges 0-10- 18pR/hr @' Used for measuring external dose rates on the Model-3 Model 153765 08/09/00 500 pR/hr or above soil surface and at one ( I ) meter from the surface Nicro-*, 44-10 l1/08/00 surface. 20-23 (i.e., initial ground surveys). NMeter NaI 2"x 2" tiR/hr 0) or S/N 147819 Scintillator above asphalt surface 25-27 pR/hr in pits and trenc hes. ('anberra L.o\\ Gas Flow N/A As needed 30% N/A Varies with Canberra Model 2400 Low Level CUP gas I.evel Proportional Sample proportional counting system was used to count c*/[* C'tountei Detector soil samples for gross beta and alpha contamination. Results were reported as pCi/ggi. ('anbciia High Purity N/A As needed Varies with N/A Varies with Gamma Spectroscopy MCA system using a high Gamma (;ermaniuin Sample Sample purity Germanium detector. SpectioNocopy Detector System I T-5

Table 4: TFF Utility Corridor Swipe Survey Results Swipe Gross a in Gross P in Swipe Gross a* in Gross P in No. dpm/100 cm 2 dpm/100 cm2 No. dpm/I00 cm 2 dpm/100 cm 2 I <10 <10 26 <10 <10 2 <10 <10 27 <10 <10 3 <10 <10 28 <10 <10 4 <10 <10 29 <10 <10 5 <10 <10 30 <10 <10 6 <10 <10 31 <10 <10 7 <10 <10 32 <10 <10 8 <10 <10 33 <10 <10 9 <10 <10 34 <10 <10 10 <10 <10 35 <10 <10 II <10 <10 36 <10 <10 12 <10 <10 37 <10 <10 13 <10 <10 38 <10 <10 14 <10 <10 39 <10 <10 15 <10 <10 40 <10 10 16 <10 <10 41 <10 <10 17 <10 <10 42 <10 <10 18 <10 <10 43 <10 <10 19 <10 <10 44 <10 <10 20 <10 <10 45 <10 <10 21 <10 <10 46 <10 <10 22 <10 <10 47 <10 <10 23 <10 <10 48 <10 <10 24 <10 <10 49 <10 <10 25 <10 <10 50 <10 <10 T-6

Table 4: TFF Utility Corridor Swipe Survey Results Swipe Gross a in Gross P in Swipe Gross a in Gross P in No. dpm/100 cm2 dpm/ 00 cm 2 No. dpm/100 cm2 dpm/100 cm 2 51 <10 <10 76 <10 <10 52 <10 <10 77 <10 <10 53 <10 <10 78 <10 <10 54 <10 <10 79 <10 <10 55 <10 <10 80 <10 <10 56 <10 <10 81 <10 <10 57 <10 <10 82 <10 <10 58 <10 <10 83 <10 <10 59 <10 <10 84 <10 <10 60 <10 <10 85 <10 <10 61 <10 <10 86 <10 <10 62 <10 <10 87 <10 <10 63 <10 <10 88 <10 <10 64 <10 <10 89 <10 <10 65 <10 <10 90 <10 <10 66 <10 <10 67 <10 <10 68 <10 <10 69 <10 <10 70 <10 <10 71 <10 <10 72 <10 <10 73 <10 <10 74 <10 <10 75 <10 <10 T-7

Tal)le 5: TFF Utility Corridor Soil Sample Results Radionuclide Concentrations (p('i/-,) Bo(k~ground N,"l*, S*ulboc'ted V-238 U-235 (,s-137 ( o-601 Th-228 Th-232 (63 Key) 144.186 Kcv) (662 Key) {( 117(0+1.3s) 12: Kc% (238 Key) (91 1 Key) Slample -ID pCi// I/ +/- (ilg 'A +/- pc/g 1 7 +/- p(i/. /P' 1 p('i/g I_ error pCi/g error pCi/g error pCi/L error p("i/g eiror pKi/g error pCi/g 20 20 20 20 20 20 (CO(RR (K0001 1.0(6 117.6 1 29 1o0 112 8 0.10 0 1I 44 7 1009 NIl 0.00 087 14.7 013 1ý5 27 2 042 2 (')RR 00-02 072 115.9 083

0) 1 ;

4618 O(6 004 117 ( ((1 NI) 0,00 089 92 ((((8 104 2193 )24 3 CO'RR-H0 03 NI) 0,00 () 18 59)5 009 ( 13 9105 007 NID 000 0.82 15.2 0.12 149 299 (19 4 (C()RR (01-04 1 44 601 (097 0 IM 54 7 0.0S 0.1( 494 805 NID 080 10,8 ),09 0.91 234 0.21 5 ('(ORR 00 01( 1(,0 ((1 1(03 NI) 0o0 NI) 0(0 NI) (0 0.59 302 0.18 144 919 04(6 6 ('()RR 9006 06 120 6(.1 ((2 0(12 592 0O7 0,12 525 (.06 0104 126) 005 0.78 11 3 0()9 ((81 26.9 023 7 (CORR 00( 07 1 59 942 1.44 1.14 746 0O10 008 1082 009 NIN ) 1 0,00 0919) 141 014 1 50 28 9 042 8 (CO1RR 0O (( 1 (M 101.2 1.04 () 1 91(9 1 (11, 1009 46.8 W)(4 NI) 0(00 0(91 ((7 0MO 1.31 22' 0 2'9 9 ('OR0 840-(9 ND O(0.00 0.10 987 0(.1 ND (00 NI) 0.00 03(( 16 5 14 1 24 16.1 045 IM COR(R-(0-O( 0 1 47 60.6 0.89 0.18 410 001 0110 48.1 0.0s NI 0.00 177 11 7 009 095 20,2 .19 II 'CORR 00-0( 11 ND 0.00 0 III 1191 0.12 0.07 99.2 0.07 NIl 0 O00 0.75 144 ().11 1.26 20.0 o 31 12 CORR0-00-012 106 828 0.88 ((12 66.1 0.08 0.A 1 521 0(1(1, NIl 0.00 071 12 I (109 072 3.18 0(24 13 ('OR R(( O-I0(1 3 1.75 678 1.19 0.13 75.7 0.10 0.18 44.8 008 NI) 000 (06S 25A 0.17 1.74 22.2 0 ( 9 14 CoRR-00014 1.39 67.2 0.93 0,12 57.7 0.07 0.12 47.0 0(16 0.09 57.2 0.05 070 14.8 (.,10 1O2 279 ((29 15 CORR-00-OI5 1.49 53.4 0.80 011 66.5 0.07 0.09 60.1 0.0) ND 0.00 0(7 112 00.8 (.81 931 0.27 T8 WW Il, tyS tl'ibly ( ( ,,y,.U Ipd

Table 5: TFF Utility Corridor Soil Sample Results Radionuclide Concentrations (p(:i/g) Ba*'k.tfrommd ;V, Subhmtre'ld U1-238 U-235 Cs-137 (o-60 Th-228 Th-232 (63 Key) (144,1,6 Key) (662 Kcv) {(1170+i330)12) Ke1 (238 Kc%) (91 1 Kc\\) Sample 11) pCi/,, 'h +/- p(,i/, 'If pCulg 'A p l/, '/ + C 4/, +/-t pCi/o,

Y(

+/- error 2 p( i/ error p(C /C error pCi/o error pi/g error pC(ilg error pl*i/g 20 20 20 20 20 16 (ORR 00I-116 I 17 732 II86 o 2' 155 5 020 007 741 Ills ND 0 003 01611 138 9H1 22.1 0 20 17 CORR 00-017 0 77 1091 1 814 0.1 74 1 01111 0 12 65 1 M18 NID 00 0,58 2 (.1 .44 27.8 040 18 CORR-0 O 1 8

1.

III 65'2 0772 11 59.1 0.07 0101 437 011.4 NI 00 151 1 0') 1170 9 25.5 0.21 19 C(ORR 010-019 1 57 908 ( 41 5 1 (( 6 0 IO) NO) ()1100 Nil 0,57 299 o17 1 63 237 019 201 CORR-00-0201 I 78 46 1 (82 O12 48.7 11.06 009 4618 0 01 ND () 00 0.99 8.6 0,09 5 61 19.1 025 21 CPRR 0-0021 1.17 86.0 101 0.20 529 0.11 0.11 75.5 (0.1g NI) ,00 0182 1I11.0 ( I 51 21.7 ()66 22 CORR 00-122 t,52 636 097 ( 16 54 7 1119 0.18 45.2 001 004 654 003 0.90 I0I) 10.109 1192 402 0137 23 CORR 10-1123 ND) 0.00 0112 768 0109 017 41.5 1117 NI) 0(Y00 O96 12A1 0A1 1,22 29.5 0.36 24 CO1RIR 00-024 182 61 5 0.94 o 14 51 9 0.O7 0.05 73.5 0,0-4 005 75.3 0,14 0.18 12 3 0,08 0.16 21.5 1)18 25 CORR-001-025 1 97 68.1 1 34 ND 0.00 0.13 50.6 007 NI) 0,00 171 14.6 11 1.12 28.1 037 26 CORR-O0-026 1.25 73.5 0.92 0.18 38.9 0.07 0.23 34.6 0,08 ND 0.00 0161 179 III 093 1 37.0 034 27 CORR-00 027 1 58 54.0 0.85 ().11 84.5 0.09 0.17 544 (009 ND 0.00 0,75 16.8 0.13 1.36 25.1 0.14 28 CORR.00-028 1.91 57.1 1.09 0 14 57.4 0.08 0.25 27.2 0107 N) 000 I'lI 10.7 0.12 1.39 21.6 01M) 29 CORRO0 029 1179 122.2 0.97 01.13 84.1 II 0.28 45,0 01.1 0.29 33.4 0.11 (68 21.9 0.15 117 5.63 0.39 3( CORR 00-0301

2.63 52.4 1538 0.19 47.3 0.09 ND 0.00 ND 0.00 1.45 91 0.13 155 19.6 151.

T-9 W :\\ml mthytl llity~i tc,,, I 2,,pd

Table 5: TFF Utility Corridor Soil Sample Results Radionuclide Concentrations (pCi/g) Bac*g,orelid Not Sub~riact,, l U-238 11-235 Cs-137 Co-60 Th-228 Th-232 (63 Kcv) (144,186 Key) (662 Kc\\ 11 1 170+130) /2) Kc\\ (2;8 Kcv) (911 Key) Sample 1) pCi/g pCiA/ I +/- pCi/ '+/-p/g pCi/h p0A+/- error pCi/g error prhn pCi/c crrpr error pCi/g error pCi/g 20 20 20 20 20 20 31 ('"RR o0.-(11 5'S3 1047 162 0 h ?) 61 0 10 (118 31g 1 011 ) (if)I

79) 15()O (178 22.1 0.17 176 232

(.41 32 CO'RR 00032 1 91 65 1 1 24 ( 17 41 7 0,07 (I II 446 1)(153 0 0 61.1

11) O(76 (7

18 (0,9 086 11.2 0.27 33 C()RR.00 018 1.1 1 ;3 744 099 021 5.12 ()I NI) 01100 NI) 1 0 0168 22.1

0. 15 1.04 37 1 0.39 34

('ORR 00 W34 1 70 5335 091

1) (2 53.1 0((6 0.07 84 3 00(6 NID 0 0(0I 0(80 11)7 0,09 I o8 191 021
S COIR II 015 o ((53 120 1 1.14 0.08 118.8 0 10

( 14 8.8 o II ND 1001 092 (34 0.12 181 221 (1440 36 CPRRP-01-36 1 76 67.2 I 19 0.13 616 0O18 16 467 0107 NI) 0O11 1176 10.9 0.08 0.83 352 0.29 37 ()R R-00-8037 NI) 0.00 0.16 600 ).10 NDI 0011 NID 0)O 1,06 12 1 (1.13 184 216 0.40 38 CORR 0-0 38 0(95 93.6 0(89 0.1( 523 ((.05 007 67.1 0,(5 NI) 0,0I 0 73 1).1)8 0.77 26.3 (.201 39 CORR R0-039 1(67 75.8 1,27 0.12 9(11

01) I 0.13 64.9 (1(78 NI) 0.00 089

14.

10.13 1(56 22.2 (135 4(1 COR R--(401 1.50 54.9 (182 116 441 1)007 NDI (H()8 ND I.00 088 11).1 009 1.97 22*2 022 41 CORR-00(-041 1.70 726 1 23 ND ((00 0.07 115.4 0.08 NI) 0.0 0.84 156 0.13 1.67 28 1 047 42 CORR- 00042 0.96 67.3 0.65 (.12 596 ((.07 0.1l 46.9 ((.(5 0 II 485 0.07 071 120 0,09 0.99 216 (.21 41 CORR 10 143 ND 0.1)0 012 794 1).101 0.14 47.0 0(17 NI) (.100 0.(78 (78 (.14 1 67 2o.2 () 34 44 CORR ( )0 044 2.48 38.7 1196 1 .(17 46.1 0.18 0132 22.7 (.07 0((9 63.1 (0.0( 193 108 (0. 10 I 1 29.3 ((32 45 CORR-)0-045 1.31 103.8 136 0.31 49.6 015 0.27 44.5 (.12 ((93 71,1) (.o9 I.9 (4 013 1.84 257 (47 \\% \\tit uWl l llhlylI.....

¢,Itd..

J,,-1 1 wpJ

Table 5: TFF lUtilitv Corridor Soil Sample Results Radionuclidce Conceniralions (pC/u.) Back rod ml Not Sublra ted U-238 1: -235 Cs-137 Co.60 1h-228 Th-232 (63 Kcv) 144.186 Kcx) (662 Key) 1(1170+1330)I/2 Key (238 KcY) (911 Key) Sample 11) p('i/g 'A +/- p('i/g '/; +/- pCi/o 'A +/- p('i/g '/A pCitc +/- pCi/g S"' error pCi/g error pCi/g error pCi/g error p('i/g error pCi/g error pCi/g 20 20 20 20 20 20 46 (')RR-.)).046 2 11 425 090 0 14 626 009 0.11 572 0 06 NI) 00)) 0181 14.7 0.12 1,04 214 0,24 47 CORR -0 047 NI) 00)) 0 15 68 5 010 0.21 40,9 0,08 NI) 1)0,0 092 162 1015 1 91 21.0 (041

4)

CORR-00-0-48 1 33 61 6 0.82 0 14 435 006 0.16 329 (),(5 0)08 329 0.03 075 12.9 0.I1) 086 24-1 0.21 49 (')RR0OO 049 1.22 7&1 095 0 )) 106A (IIl 3 033 (38 11 ND 0)00 084 135 til1 1.2) 30)7 040 50 (CORR0 0 050 179 120,8 2 16 009 859 0198 (16 285 005 01M 6017 (08, 070 13.6 0()10 086 1)13 o26 51 (PRR 00 051 NI) 0111) (III 82.9 0.(09 0.08 794 0(06 NI) 0(Y00 088 12.4 0 11 1.13 3(.8 (35 52 CORR-00)(152 1 )9 81,9 0.89 0)17 38 3 0107 (110 50.3 005 NI) 0.00 0 6t 120 0.08 0.91 24 5 0 22 53 CORR 00 053 1.77 64.8 1.15 1 13 675 009 ND 000 ND 0.00o 076 18.3 0.14 1.5( 20, 0(31 54 CORR (-O 0((4 ( 47 103.6 I 52 0.10 591 0.06 ND 000 NDI (0.00 ).81 10,8 0.09 ((89 25,1 1.22 55 CORR-00 055 NI) 0.00 ND 0.00 ND 000 NI) (0) 0.96 12 7 0.12 I 23 26.0 0.32 56 CORR-005050 1 90 53.4 1.01 (.11 73.6 0.08 0.18 36.3 0 (0(7 005 77.8 01.04 1.72 14 1 0 1() 0.91 26.4 0.24 57 CORR-00-057 ND 0.00 NI) 0.00 0,07 112.5 0.08 ND 0.00 ((82 13 5 (.1 I 1.4(6 27 0.2 58 CORR-00-058 1.34 92.5 1.24 0,10 90.0 0(09 0.15 53.91 0.08 0.08** 101.1 0.08 M175 14.6 01A1 1.43 296 (142 59 CORR-00-059 1.29 83.1 1.07 0.21 47.1 (.10 0.16 45.8 0.07 0.16 6539 0A I LIM ((.4 (((2 (1.3 03 0.33 60 CORR-00-(60 0.96 109.8 1.05 0.15 58.8 0.09 0.20 36.2 0.07 ND (((0 0.78 14.5 011 1.26 35.2 0.44 his value is for Cs-134 W A\\III wtilily~llt Uitilty -,Illdl IL~ I~ pd T-I I

i I. h Z I I C' IC' '4 IC' fl fl r -I-- x X x

i. I LhI.

C Z Z C C Z v C 5 5 5 v - 4-4 S C C 4-z z z 2 -J C' .C 1 .C 1. 4 I -5 1' 1+ 'IC ccc cc 14 c C C 4-1-. 5'. Z OC C' C' 4 14 -4 C 4- - A 4 C' 4 -j C 4-4- '.4-' -5 C c c c c c S c c S S S c 'IC -5 C C z c C z c c 'C 'C C'-'-'-c' CC C' C C 5' ) IC A C' C -4 -4 -4 I. IS-i C A C 00 4-C' S C' C S C IC -CC4-C4'Q '1+ 54 C C c C 4 c c z c c z z z z z c z z 'IC -J + C C C 155 4-4 C C 4 4 C IS 4 'C C C C -4ccC-4CC CCC' C IC C 4-IC 1- 14 C 4-C C' 4- -CCl4XC 4 C 14 CC 1,4 14 c 4 4 -4 Cl 5' IS C IC 4, 14 4-14 5 5' 4-4 C 4 C CC F t e -4 4 414 4 1-4 A 11hz IL Al III IIFIZEEN 4-4 -i-' '4 C Ic 4-IC I-C 1+ 'CC Il I'-) 'Jm 1 -I C -I C-IC 41 IC 5 1 1

Table 5: TFF Utility Corridor Soil Sample Results Radionuclide 'oncentrations ip('iig B*k-cl{,mt Nwn Sl'timle<d U-238 U-235 Cs-137 Co-60 Th-228 Th-232 (063 Kcvl (144,196 Kc%) (662 Key) J( 1170+1330))/2) Key (231 Kc\\) (911 Kcy) Sample ID-p('i/g Vf +/- pCi/g +/- P(-'ig 4 pCi/. / +/-- pCuiy 1/ +/- pCi/o '4+ error pCi/g error pCi/g error pCu/p error p(>ig eror p'i/e error pC'/L 20 20 20 20 20 20 76 CORR 00-1176 142 100.8 1 43 021 644 0 14 (1 2) 42 (IA.12 NI) 0") 00 09s 21 5 0,201 16') 25.7 0.43 77 ('(CRR 00(077 1,64 694 114 0 18 5332 0 IM 1)28 32.4 009 N) IN 10 00 10 I') 9 0 12 1 19 38.6 046 78 ('ORR-0)) 1078 215 60.4 I 10 0 17 493 008 0.12 707 008 NI) 000 (085 161.0 1-1 22 274 0(33 79 ('(RR 0 O1)79 171 600 1M1 0 1)8 478 009 0.12 583 1 0 07 0,1 s 6.6 0,08 (174 146 1.1 l.1 2335 1),.

81)

C)RR 00 080 NI) 0.001 0112 78.6 0+09 0(21 16.8 9 008 NI) 000 0.85 13 4 0,11 I'M) 28.2 037 81 CP-R 1 0-081 262 476 1 25 NI) 0100 0.10 72.7 0(07 NI) 0, 00 091 12,6 0.1 1 28 266 0 134 82 C()RR-00 082 117 81.5 093 0 18 497 0,09 NI) 0.00 NI) 0,00 0 85 (65 (1 1 1.57 231.0 0)6 83 CORR-8(0083 197 71.4 1.41 0220 43,6 0(09 0.11 58+8 0106 NI) 0.(0 114 10).) 0i1 182 88 0)34 84 C(ORR 01) 084 1.25 902 1.13 014 654 0.09 NI) 0o00 NI) 0,00 (15 12,5 (.12 177 22,5 0.40 85 C()RR (0-085 154 78.7 1.21 0)12 65.2 0108 (.09 70.9 0.06 NI) ooo o075 22,8 0.17 149 2).0 0(30 86 CORR 00-086 1 49 80.7 1.20 0.11 82 5 0(09 0.33 228 0,08 NI) 0ooo 1.87 123 (Y11 1,4;2 21.8 033 87 C(ORR 1-.)087 2,11 59.9 1.26 0.15 718 0.1I 0.17 54.7 0.09 ND 0(00 089 16.5 015 1 69 2.).2 0.39 88 CORR 00-088 NI) 0.00 012 58.7 0.07 0.24 319 0.08 ND 0.00 1)08 1).7 0.12 1.72 207 03(6 89 COR R-00-089 1.60 74.2 1.19 (.13 665 0.09 0.16 65.2 0.10 NI) 0.0I 0,90 166 0.15 1.56 235 0.37 90 CORR 00-090 1.57 71.3 1.12 0w12 76.2 0.09 0.14 73.9 0.10 ND 0.00 ) .98 122 0 12 1+43 25.5 030 T-13 'A':\\III tllllil)\\tll tlllllly {tlllld4*l *l+il t, *ltl

TIable 5: TFF Utility Corridor Soil Sample Results Radionuclide concentrations (p('tvg) BacuAground.At Sttbtrmi il. IJ-238 1-235 Cs-137 Co-60 Th-228 Th-232 (63 Kev) (144,186 Key) (662 Kev) { 1170+1 3 30) /21 Kc,ý (238 Kc) (911 Kcv) Sample pci/g '4 4 p(i/z '/ +/- pCi/g c/ +/- pCi/az '4 +/- pCi/g Ci +/- p~i/2 '4 + error pCe error pCi/L error pCi/g error p( Ci/ error pCu/ ernor pCi/, 20 20 20 20 20 20 I91 CORR 001091 ND 0 (Y00 069 61 ) 0.42 0,15 6)16 0I.09) NI) 000 0.82 13901 II 1 11) 3140 0.137 92 CORR 00-092 NI) }0}W1 () 13 71)5 (109 0A.1 73.1 008 NI) l) 00 I1I 11.6) 0 13 1.98 17.60 0.35 93 CORR-00-093 316 476 I 50 0.13 74.5 0 10 0.07 99.3 o07 NI) O1(J0 1)2 0 1)50 012 1.93 1870 034 94 (COR R 00) 1194 076 10O22 078 O. 10 8L5 0.08 NI) O)0) NID 0)1)1( 1170 12.60 0,09 117 2010 024 95 ('ORR 00(095 I 19 81.5 0)97 0.II 90.3

0. 10 NI) 0,00 NI) 0).00) o174 12.80 01.09 1,20 24,501 029 96

('PRR 00) 096 0.74 109.8 081 NI) 0.01 NID ) 00 NID (}) 00 9 D3 12.80 10AI I 501 25.60 038 97 C(}RR-}0O 097 2.19 49.8 1 09 0119 44(6 0(08 0.15 55.4 0)08 NI) 11)00 1 25 10).80 0.1.1

20) 19.2) 1)39 98 (CORR -00 0198 2.17 544 I 18 0.07 92.8 0,07 0.35 29.9

0. I1 0.05 129,3 0.)6 0.79 18,90

() 1 1.32 267) 0135 99 ()ORR-00 0199 078 9 18.3 0.92 0 13 73.1

0. 10) 0.40 276 (A 1 0.12 54 2 0.07 092 19.90 0.17 1.70 22.70 0.39 100 CORR 0{}-10(0 1.28 90.9 1.16 0,18 52.0 0.09 040 21.4 (1.09 NI)

))0.00 105 1260 0.113 I 76 20160 0.36 101 C_'OR R 0}{1 101 1.18 967 1,02 0.13 66.7 0.09 0)36 24.7 01)9 NI) )11 0.92 11.60 01l 1 3 25.50 014 102 C'ORR 0I0 10)2 NI) 000 0.21 60.9 0.1. 0.29 29.5 0.09 0.16 712 0A 1 099 13.60 (113 1.42 23.40 0.33 103 CORR 00} 103 256 51.2 1.31 0.15 7310 0A11 0.24 36.5 0.(09 0.16 64.4 1 1.; 131 9.70 0.13 1.93 21.40 0,41 104 COR R 1044 2102 62.0 1.25 0,18 54.9 0.10 0.34 29=4 0.1) 0,13 66.6 0(09 1.011 I1.90 0,12 1.62 21 40 1)35 105 CORR I NI) 000 013 567 007 0.18 375 0.07 NI) 00 161 11,60 (1(7 088 27.80 (124 T-14 'A' LII woilly~tl til idly....... H 1 ti ? 7 wpd

Table 5: TFF Utility Corridor Soil Sample Results Radionuclide Conccint ral ions (p( i/g) Sckp 1rmdi,, N' %'.,'ohI/ l led U-238 U-235 Cs-137 (o-60 Th-228 Th-232 (63 Kev) I-4, {1 i Kcv) (1662 Kev) 11] 70+131())/21 Kcs (2,8 Kcv) (91l Kc\\) Sample II) 1h '7, +/- pCi/g A +/-= pCifg 'A +/- h / 'h'i/, error p'i/g ciror p)0g croi PO/rr p C I/g error pCi/g r ror p~i/ 20 20 20 20 20 20 I(6 C(ORR 1) 1O06 ND) O0O1 ( 12 6'9 1 008 O 1 28,2 (105 NID (H0) 0 9 I 0625 O() I 0, 2260 "24 (07 'ORRS 00( 107 NID 000) 0 (0K III 0()( 009 05.1 10.3

0)

(O(17 0776 I 1.80 0.O') 1 2' 4500 0).55 108 C(RR-O 0)101 ND (I (H) i2o 455; 0,09 0.43 20.4 (,09 (27 1282 00o)8 (092 10.90

0. 1(I 1.4 2971)

((3 109 CORR O0 10,) 201 630 1 28 ((07 119) O18 (721 4495,5 N NI) I 1. 1060 012 1 S.; 25 go ((7') 110 CORR 00-I 1O 1 78 57.6 IO ( 0 15 01 2 0( 0(124 7303 (007 01g) 41 0oo7 (89

t11, 0110 I

25 2370 0,3( I ll C PRR 4(- {Il I 1 31 2.1I 1 ) 0 19 5Ol o ().Is 19 7 0 07 0 II 74,8 0 1,00 1140 (111 1 -10 2340 O.3 112 COR R 00- 112 081 10(04 (X) (16 SI I 0((8I 021 I 7(14 0 1( (((6 (), 1 ( 7 0,0 o((II I 2 11)1) 1( 113 CORR ( )).I I A 174 55.8 0.97 0 14 77.; O1I NI)D 0( 00 I I 1 75 0 (((1 I 9,60 0((4 1106 713) ((90 114 CORR-t()}- 114 1(07 1132 1.21 (013 79.6 W11( 0.21 38.9 0.08) NI) -1 4 8,90 (((4 101 19,00 ((1 115 COR -(R 0. 1 15 22 79.6 o.97 (.12 62.0 0.07 0.24 33.7( (.()8 ND 0.111) (( 092 1 LA1 ()I() 1 7() 1750 ((Y1 116 COR RR -O-116 1.19 112.1 1.33 O13 72.3 (09 0.15 85.(1 0.11 NI) 0.00 ((91 1 1(10

0. 12 14')

262( ((9 117 C'ORR t00 117 1.15 71.5 1.32 0.17 66.2 0.1I 0.30 2378 01(7 ND N)00 1,04 10.60 ().1 1.54 251 ) W 118 COR, R (0 11s ND) .0M 0.14 70J) O) 10 0.22 53"2

012 1NI) 11,0 0,1 14 A 10 0 1 19-1 1.79 73.7 1.32 0.19 58.0 0.10 0.28 2.8 0.8 ND 0.1 1.01 11 3,0 o4 1120 CO RR -t00 120 54.9 1.3 0.2 7

0.09 4521.4 ND00 5 118 ,7 2, 0; W itlt milly\\ill otht) -- d.11 ý,* -0o il d T - 15

Table 5: TFF Utility Corridor Soil Sample Results Radionuclide. Conc'entrations (p)(i/g-) Bue-A,,,ound Noq Sulmucte'(d U-238 U-235 Cs-137 (o-60 Th-228 Th-232 (63 Kc.) (144, 16 Kesj (662 Ky) {( I 170+ 3 },30)/21 Kc\\ 123, Kc, ) (91I Kcv) Sample -ID p pci/g +/- phi/ / p(/g p(i/ pCi/. 1/1 .t error p(i/g error p(i/g eTreor p( er P04-, p('i/o error pci/g 20 20 20 20 20 20 121 ('ORR- (-II121 3 I 1 s I 55 014 496 ,07 0 04020 4S1 7 ,910 1 46 940 0,14 I)9 2'060 0.40 122 ('ORR- ) 122 NI) 0.0)0 ((24 56, 1 ) 11

1) 17

49.

0()08 NI) L.10 147 90)0 O 14 2.11 18.90 11411 12 ('CORR 011 123 NI 1.10 0 14 689

0. I (1.12 8(0 0 I)M NI) 01)0 1.30 II 20 015 2 82 17 20 040 124

('(RRO0) 124 1 12 9)8 1 (s 0() 6915 ).91) ().39 264 {1 1' 670 1.08 0.70 2'(60 0 17 I 6 2370 0.32 125 CORR 00 125 1 71 7481 127 0,I9 SO R011 .1131 3104 (11)9 NI) 0.00 1.1-4 1090) o 12 1 69 19.50 (.(1 126 CPRR 100 126 (88 11 I I )10 019 586 0A11 33 3814 1A NI) ((00 1 21 11O 01 1 1 94 20,20 O(9 127 ('CORR 0 127 209 72 1 1.51 (28 843 0.1(1 0.40 21.4 (09 0 9 8)2 0Os I (w9 880 0I12 I 91 188) 0(36 128 (ORR 0ll) 128 2 is 61 9 1885 1)6 617 0 I10 0.25 3889 0} W 00)8 71(1 1).6 I l.O0 10 2o I I I 02 22.10 O30 1 129 CORR 00 129 0)81 117.3 0.95 1.17 54.7 0))') 0.42 238 1o NI) 0(0o 1((4 12.808 1 1.05 225) (1(7 130 CORR 0) (130 068 121.1 0(82 008 96.7 0.08 ND 0.00 NI) 1X) 0.78 17o00 o 11 1.28 26.40 ((84 131 CORR-O0. 131 1.35 74.6 1M1 0.10 95.o( 10I0 0.08 96.5 1.18 NI) (0A) 0.96 13.50) (13 1 38 29.6) 0141 132 CORR 132 091 11189 0.95 1.20 58.5 O 12 ND (0.00 NI) 0(00 0(87 1290 0.I I 1 42 21.40 1)3(1 .3 (ORR-{)()- 1388 NI) 01)00 0(16 55.9 0.09 ND

0)

NI 0)00 0(87 1681 (18 1.27 31200 0)41 14 ('C)RR-00]- 134 0.82 1127 0.92 0.09 77.7 0.07 0.18 55.5 11 NI) 0,010 0.90)O I .00 0A1 1 23 2760 (((4 135 CORR ( 135 1188 1121 099 (107 123.0 0(09 ND 0)1) NI) 0(100 059 29.30 0117 137 27.20 0(37 T-16 \\1 ti11,1I1y\\) Il I ty d, I 9, 11d

z Iz PH Hz IT k 'C7 7 z E 7 7 z 7t7I117117r71Y17r7r7II7TT'-4 75 4-~ ~~~ 4-1 -I C C -C -2 4- -2 4C~ -C12 4- -C C- -141 C C z 0 S z zzz z z 7 z z 3.4 12 4 -2 -4 t2 - 1Li 02 7, O C -1+ I 211+ 717 -1. 21 I I II VT 111 21 21 21 2-2111 4 H -'1+ 7,.k -I

0.

C C,

Table 5: TFF Utility Corridor Soil Sample Results Radionuclide (oncentrations (p('i/,) U-238 1U-23. Cs-137 ('*-6(I Th-228 Th-232 (63 Kcv) 144.196 Kcy) (662 Kcy) U(1170+1 21 Kc (238 Kc\\) (911 KcN) Sample 1.) pCi/y '4 i '4 +/- pCi/ 1h +/- ICi/t +/-i p('i/g (4_ crr r Ci/g ,rL p(i/g crror p(C/,N,

crm, 1,(

crror p(Ci/ Cor 1)('i/, 20 20 20 20 20 20 151 CORR) 00 151 2,38 75 5 1 SO 09 1014 1019 0 12 962 0 12 NI) 08ý 12 01 1 I 54 199 0,31 152 (ORR (I0 1,2 106 117 7 1 25 006 11017 0)17

0. 10 1

669 1007 NI) 80 O0 l 12.3 0 10 1,59 22.3 0135 153 ("ORR 00- 15.3 175 887 1 55 o 11 640 ). 1)O NI) o))) NI) 0 9 13.7 11.12 1.-13 20.9 038 154 ('ORR O0 154 146 82.5 1 2 8 008 923 0.07

0) 10 616 0I, NI) 0,0 0.76 179 o 14 II) 27.5 O3)9 155 CORR-I)) 155 NI)

O3)06 1 1 1 5, 7 1.07 (Y06 106.4 O1)6 NI) 1)9 0O00 IO 106 30.7 (9I1 1515 (UORR.01 16 1.50 799 I 20 0 1.1) 62)) 0,1)8 11.)6 61.5 OIM NJ) (1 00 (1,77 178 1)14 1 92 24.6 017 157 C(RR-O0- 157 I 03 779 0.80 0.1M 74 2 0.07 N) 01100 NI) 0.011 0179 177 1 14 1 46 22.9 0.13 158 C((R-10-I (8 1.28 892 1 14 0I I( 916 580.0 0.07 98.4 007 NJ) 0))00 017) 16.9 11)2 1.28 194 0.25 159 ('ORR-)O-105) 2,0) 676 135 01.16 499 0.08 0(19 35.4 11017 0o7 11.2 (18 0)94 II.I 1101) 1.26 26.4 0133 16 (1 CORRR 160 1 45 101.3 1.47 0ils 434 0WA NID 0,00 0,12 686 008

09) 141 0 113 1,67 195 (133I 161 CO(')RR 00 161 1.22 1062 1.30 0 12 71 6 0,09 ND 1)0)00 NI)

(000 098 III 0 II 156 23.5 4117 162 CORR 00 162 1 18 933 1.29 0.14 68.5 0I)0 NI) 0110 NI) 000 0179 196 0.12 1.7) 17.1 (..1() 163 (OR R-161 NI) 10.00 0)09 002 0.09 ND 0.00 NI) 0.00 0.87 21.3 0.19 I 32 194 029 164 CORR 00- 164 1.06 114.5 1.21

0. 1L 66.2 0.09 ND 0.00 NI) 0001 1 0(

10.4 ,115 198 234 ,1)7 165 CORR-00 165 1.13 115.3 1.30 0(13 77.2 0.10 0.11 66.5 007 NI) 0W.0 1.02 1.0 1116 171 2(9 )17 T-18 \\*

111 hlyVlII vl'thly.....

I~,,Il I I I'~d

Table 5: TFF Utility Corridor Soil Sample Results Radionudid (Concentrations (p(i/g) Bra'kl, ,rmd A,l Sihllyla, f'd U-238 LI-235 Cs-137 (6o-60 Th-228 Th-232 (63 Kev) (144.1 6 Kcy (h62 Kcv) [(1 170+1 3,)0 K 12(8 Key) t91 1 Kcy) Sample 1I) p(.'i/g +-- / +/- p/g 'A +/--p.ig

4 pUi/g p(.'/

+/- p( 'i/g 'A error p Cig error p(u.il ciror i ( erro ror p C

ci10, P('i/g 20 20 20 20 20 20

161,

('O)RR 00 l66 1 8.4 7S I 1 18R o 1-1 894 O13 O 0 749 0(1l7 No) 00~l 1 1 11 (I) (112 1 0S, 21 1 03t) 167 (C NR 00I-11,7 1416 16 1 1) 021 1 42 9 I)09 117 0, 7 61 10( NI) on I (w4 12.1 0,11 1 94 210 041 168 (CORR<(.O II0)6 ND I0 00 (,0 I(06 I I) ND 001 NI) 10 N 085 1,6 1 ,114 I l8 2810 0,39 169 ('ORR-0 1I t,9 1 76 9 0 1 72 0 12 68 I O. NI) 00)0 ND ).00

12) 90 012 215 187 0,110 170 CORR0(0) 170 1 M 7101 1 21 017 51 1 009 1)05 IO31

o1111, NI) 0.00 III 11o2 011 1751 222 0.35 171

('O1(RR 00 171 NI) () 00 0 M 6O 174 )007 NI) 0 o00 NI) 011( 0 ,)o82 171 0,I) -1 1752

22) 1)7.1 172

('ORR 00 172 I 18 104,6 1.23 0.09 1096 0O10 NI) O00 NI) 000) I N5 1(106 (.12 1 69 20.0 0,14 173 C(ORR 00 173 NI) 0.00 N.0 I (0100 NI) ( 1010 NID 0)00 1 10 I 0 0 12 143 25.o 0 16 174 CORR-0() 174 NI) 18()

0. 12-851 010 ND 0O.001 NI) 000 0,8; 1.73 011 I'Il 26.7 0 W1 175

('CORR.00175 1.19 92D I.19 NI) 0.00 NI) 000 ND 0.00 ()93 132 01I2 1.2o 17 8 (01, 176 COP R-0O0-)176 2 26 6210 140 0)23 36A4 .18 0 0.09 113.9 (010 ND 0.<) 0.03 1.106 n 11 1.6,8 22.2 1 37 177 (CORR-00-)177 ND 000 0.1() 739 007 NI) ll) ND 0.00 0.90 1.1 0112 1 29 26.0 01)7 178 CORR-0-)178 NI) 000 0.13 71.3 (19 0.09 113.9 0, 10 NI) ,00 0,90 11.6 012 I 40 26.1 0.17 179 CORR -0 0- 179 1.81 596 1.08 11.18 57.2 (.10 ND 0J)0 NI) (00 I.18 10,8 01.; 1I49 300 046 180 CORR-000 180 1.08 103.3 1.12 0.13 79.5 0.10 (12 11.)8 0.12 ND 0.00 1.91 13.8 0.26 1.52 24.2 0,37 T-19 W :tl thy*lulnliky dq x il 12,,A

Table 5: TFF Utility Corridor Soil Sample Results Radionuclide Concentrations (p1Ulg) Buc.".round N,,1 S11l11.-infd U-238 U-235 Cs-137 (o-60 "h-228 Th-232 (01 K', (144,186 Kc,) (662 Kc.) j 1170+1 "1,30/21 Kc% (2.8 Kc, (91 1 K! y) Sample1 i) pCi/g pCi/g s -h pCi/g 'I +/- p(i/) / p('i/.g +/- error ro error pr'/r CUM p(il ror pCil. error p( ilg error p(?i/A 20 20 20 20 20 20 181 (CORR o0 181 NI)

1) 00 0I22 542 012 NID O0)(}

NI) I) I 55 9.6 o,15 217 24.' 0.52 182 ('{RR-1)1. 1)2 ND) () DD (0 Io( 1 692 0107 NI) 0 00o NI) 0.100 I 04 1 6

2)

I0 1.58 225 o.3 6 183 C{ORR 00(I 181 1 51 94.1 1.41 0 18 60 7 0(II (10)9 1 I 1 1o7 NI)0 0101 1.07 117 0 13 1.54 243 O 17 184 (')R R 00(}-8-! ND O0 } (i) .21 50.6 0 11 NID 0.{N) NID 0.o00 1 ;1 8 7 n}. 1 190} 16.9 0}.32 185 (CO)RR o) 105 W 196 754 ( 41 0I,9 48 3 0,09t) 0.17 928 0,07 ND 0,)00 1 17 II) I 0 11 209 18 3 0.38 186 C'ORR 0 1I86 2 1) 682 1)9 039 43,0 (.17 NI 0 00 NI) N 0.0 ILos 1206 D1. 2,05 23.7 1.,19 187 (O 1 R I-0 187 I 019 95 I I 104 I.15 601I 0.09 0119 10011 1 09 NI) 1 0 00 I1II 10}9 012 1 29) 277 I Y1, 181 (C(ORR 0(1) 8I8 1.78 67.6 1 2o) 0)20 4310 0.0}9 NI) ll NI) 0.00} 11.01 11.0

0. 1 157 19 6 0ISI 189

('CORR 00 189 1(04 1139 1,18 NI) 0}01 0.11 71.1 008 NI) 0.00 1 1I-I.1 Il1 1.71 243 0.41 190) -((R R O0 '190 1.67 68.8 I 15 022 55l] 1112 0.14 69.1 0 l10 NID 0,.001 0.90 17.9 0.16 1501 284 0143 191 ('(I)R IS O-191 171 852 146 0)21 61.8 0(13 O181 435 0}08 ND 0(}(} 1.10 16.3 10.1 1.89 209 0.411 192 COI* R 192 171 75.6 1.29 0.15 64.0 0} 10 1.16 560 IY09 NI) 0.00 0.91 17.1 0.16 1113 22.1 0.40 193 (URIR 00)- 191 0}.97 111 0 1.098 016 62.2 010O 0.17 45.2 0).08 NI) D} I I0 11.11 100101(4 239 039 194 CORR-00}-194 129 69.8 0.9)0 0.17 61.2 0.1}1 0 ).10 85,8 0}.{(9 ND 0}.0}0 0.19 12.3 0 11 I.6 261) 0 13 195 CORRI),- 195 1.06 107.7 1.14 (.201 54.4

0. II 0.09 109.3 0.10 ND 0,00 071 17.2 0113 I.

24.5 0137 T-20 W :Alll tahlylWl t.lih1y -)I~

1",, -

1 1 1 Pd

Table 5: TFE Utility Corridor Soil Sample Result Radionuclidc Concuntration, Ip('jilg) ].wAt,*,r*,,. d w St b'ihrat tw'l 11-238 U -23i Cs-137 ('o-60 Th-228 Th-232 (63 Kcv) 144.18M Ký'*) (662 Kev) (1 170+133O)/121 Kcy (231 Kc\\) (911 KcS) Sample I!) p(ui/g h pCi/ L +/- p( i/g +/- p'i/i +/- p(h/2 +/- p('i/g 11 + error pCilg e.,rror p(.'ig error p(i/g crior p(C c'o perror error p('ig. 203 20 201 20 20 20 196 ('()RR 0O))196 1 2 ) I2 l, { 5P1)8 00)8 021 SI 7 O 12 NID 0 1 I )15,0 0(.5 1 93 18.4 O)6 197 ((RK-00 197 15 I0 I I N 22 NO 00 01I5 69.8 010 NID 00 1 15 11 9 0 14 I 50 24 4 037

19)

C'ORR 00I 198 1,6) 63,9 55 0,1(1 0108 I119,8 01{ NID 00 09 12 3 0.12 1,80 21. 01)8 199) ('(ORR-I-199 181) 738 1 4 0 1.3 828 0A I () 11 75 () ID0 NI) 0 I 081 17.5 () 1 159) 21 8 0.35 2010 ('HORR 00 2f)0 1 6, 790)

2) )

0 17 0,7 2 0 1 ) }15 62)) 00)) NID (Y00 06 11.61 I 45 2)5 0 (,1 201 C('ORR 00201 124 91 6 114 () I 599 009 0,18 481 005) NI) 0)0)0 0.95 122 2 O12 1 21 312

0.,8 202 (OR R 00 202 NI) 0)00) 019 51 2 0,10 1)2.20) 39)6 008 NID 010 1)15 0, 1 1 1 2 18.115

) 14 203 ('(ORR 00 201 1.71 65 1 I.II 009 917 0,08 I11 777 0.0) NO I00) 9).1 12 5 0212 12o 298 0).31 204 COIRR I00) 21)4 NI) 0,00)) 1is 58,8 0A11 0.08 114.2 00{9 NID I})) o1)10 8 213 9 114 155 30.7 0141 20)5 (((RR 00-205 1.13 119.6 1.35 0.14 57.2 0108 ND )0 00 NI) ())00 1)00 11.8 0 14 19)) 245 1)2 206 OHH kR-0i)-206 NID 11.0() 0.10 97.7 0.i)0 NI) 11.00 NID 0,0 193 14M1 0I13 I 5.1 25.8 1)41) 2017 ('ORR-O0} 2017 2.65 66.2 1.75 0.09 1177 0.11 0.16 69,1 0A11 NI) 0.00(1 091 131,8 0.13 1)4 3312 i1.14 2018 (CORR-H {}2)08 0.90 123.3 I.II 0.25 40.7 0.10 0.13 48.6 0.06 NI) 0l(H) 1)1) 144 0 13 116 35.9 0142 209 CORR-1}0-2119 ND )0.00 01lM 100.7 010 NI) 0.00)) NIO (} 0 188 15 9 0 14 1 70

28) 1).-4 210 CORR-{)11 210 NI

().000 0115 56.7 00.}9 ND I ()}{) NI) I ) 1 { 1 7 141) ( 13 1.47 21.)

0. s T-21

/ \\ll luiliL**"XHI utillly *Ollltlc+l *cll L{ wild

Radionuclide Concentrations (p'i/g) Background Not Subtracted 11-238 U-235 ('s-137 Co.60 Th-228 Th-232 (63 Kev) (144,186 Key) 0662 Key) 1(1170+1330)/2) Kcy (238 Key) (911 Key) Sample ID pCi/g _f p(i/g 'I +/- p0i/g h

t pCi/g L A

+/- p(i/ pCi/g 1'/ error p('u/g ci ror pCi/g error pCi/g error pCi/g error pCi/g error pCi/g 20 20 20 20 20 20 211 CO)RP k 0 21 1 25 8440 1.05 I s 69 6 0 D1. 596 10.09 NI) (M1) 0)9 124 O ll 114 ,62 041 212 CORRk-(-212 2101 51 6 10118 103 0011 ND 0.00 NI) ().(N (188 119 .I) 1 35 22.9 o31 21.3 CORR-00-213 1.13 93.3 094 I)10 79.1 00 1 0 14 44.1 0.06 ND 0 W 0,76 116 2.1.46 20.6 0.30 High 3 1( 47.6 1.) 1.9 61.0 0)42 176 48A 0.87 020 334 10)i) 191 19.8 10.26 2.32 19.8 0.26 Low NI) 0.00 ND 0il10 NI) 0 (H) NI) 0.00 1 57 299 017 081 3.1 U7 Average 1,1 0)9 0I14 00)9 o 15 0.07 0,02 002 o 9o 0 12 1.40 035 Nominal Background 2 26 0,19 0)9 NI) 21 1.72 Niow: The Highest and Lowest values preseiined above are for eachis1(1 ipe ard miiay n)1) ocnu si Iolie samlle samlple. ND = Nol detecled, <0.1 pCi/g Cs-137, <0.I pC(i/g('o-60, <3.( pCi/g U-238, <0.3 pCi/g (U-235 T-22 "Fable 5: TFF Utility Corridor Soil Sample Result "*,. 1 M I,l iyll uI.,ii...... idJ, It I, S pd

Table 6 : Gamma Spectroscopy Results of Background Soil (Surface) Samples Radionuclide Concentrations (pCi/gm) - Results +/- 2a-30 Minute Counts Sample 1"7CS ()Co 'IT'l 23 Thi Total 2MIU 235U

11) 661.6 keV 1173 keV peak 238 keV peak 911 kcV peak Thorium 63.3 (92.7) 144 (186) keV peak 22'l'h + 23:'rh keV peak peak X-I ND ND 0.71-+/- 0.07 0.97 +/- 0.25 1.69 1.17 +/- 0.77 (0.13 +/- 0.06)

X-2 ND ND 0.90 +/- 0.13 1.49 +/- 0.31 1.49 1.91 +/- 1.18 (0.13 +/- 0.08) X-3 0.06 +/- 0.04 ND 1.49 +/- 0.10 1.56 +/- 0.25 3.05 1.45 +/- 0.80 (0.23 +/- 0.09) X-4 ND ND 1.52 +/- 0.23 3.22 +/- 0.61 4.74 3.74 +/- 2.18 (0.28 +/- 0.17) X-5 ND ND 1.92 +/- 0.17 2.41 +/- 0.53 4.33 (4.49 +/- 1.64) (0.32 +/- 0.16) X-6 ND NI) 1.02 +/- 0.08 0.96 +/- 0.23 1.99 1.31 +/- 0.80 (0.14 +/- 0.06) X-7 0.13 +/- 0.08 ND 1.59 +/- 0.14 2.40 +/- 0.38 3.98 2.16 + 1.48 (0.18 +/- 0.10) X-8 ND ND 1.44 +/- 0.28 1.40 +/- 0.28 2.84 2.30 +/- 1.16 (0.14 +/- 0.09) X-9 0.09 +/- 0.08 ND 0.89 +/- 0.10 1.27 +/- 0.31 2.15 1.59 +/- 1.05 (0.10 +/- 0.08) X-10 ND ND 1.29 +/- 0.11 1.52 +/- 0.36 2.80 1.10 +/- 0.96 (0.16 +/- 0.08) Notes:

1.

2.

3. Soil samples were collected on 06/05/00 and 06/06/00 By Ed Rudgers off GA's site but close to GA. Samples were counted 7/20/00 through 7/24/00 for 30 minutes (same count as the soil samples). ND means: < 0.1 pCi/g for Cs-137 < 0.1 pCi/g for Co-60 T-23

Figure 1: Main Site and Sorrento Valley Site Building Numbers Building 1 Building 2 Building 7 Building 9 Building 10 Building 13 Building 14 Building 15 Building 19 Building 21 Building 22 Building 23 Building 25 Building 27 Building 27-7 Building 29 Building 29-2 Building 30 Building 31 Building 31-1 Building 31-2 Building 31-3 Building 33 Building 33-1 Building 33-5 Building 34 Building 34-1 Building 34-2 Building 34-3 Building 35 Building 35-1 Building 36 Building 37 Building 39 Building 39-1 Building 41 Building 42 Building 45 Building 63 Building 64 Building 65 Building 66 Building 66 Names Administration Science Laboratories A. B. C Cafeteria Experimental Building Maintenance Building Technical Office Building Technical Oftice East Technical Oftice East Swimming Pool Building TRIGA Building TRIGA Fuel Lab Building Hot Cell Waste Yard Building Experimental Area Experimental Area Experimenial Area Emergency Vehicle Storage Building LINAC Complex TRIGA Storage Building Neutron Radiography Building ECF Critical Building Storage Building Fusion Building Fusion Lab Building Fusion Building Annex 5 Fusion Onublet Ill Building Fusion Doublet III Capacitor Building Fusion Doublet Ill Lab Building Fusion Doublet Ill Storage Building Test Tower Building Facilities (Shipping & Receiving) Building Blower Assembly Building Sorrento Valley Building Sorrento Valley Building Storage Building Raw Stock Facility NDT Facility Helium Circulator Test Facility 3550 Dunhbll St 11030 Roselle St / 11040 Roselle St / 3520 Dunhill St 3510 Dunhbil St 1b / Z/ 1 C. SITE t Uj cc cc UCSD LOTS FENCING PROPERTY LINE 0 250 500 750 1000 SCALE IN FEET N A W*L E V S SITE OPEN SPACE

Figure 2: TFF Utility Corridor Relationship With Other Facilities/Sites N W S4K E S Torrey Pines Ni ,,", (TPNE) K 20 Bulding 22 Former Hot Cell Site Building 21 TRIGA [ __ 7 7 7 '7 .7 '7 7 Open Land Area I Soil Staging Area

* '->:~...

F *. Released: t:

nres:ricted Use

Aj Building 27 4 tW A

1.

cm = 15m = -50" ............!!!i

Figure 3: TFF Utility Corridor Classification N A W* -E s Torrey Pines Northeast .-, (TPNE) ,2.,06ng ,,20, Buenddng 22 Former Hot Cell Site

Building 21 7

7 7 7,,.' .7 TRIGA v/ NOJ-SUSPEq AFFECTED AREA /T F = Unaffected Area Non-Suspect Affected Area _7 = Not included in TFF Corndor Servce Soil Staging Area -LlNA-C --Larrd Area 1I: ctT = 15m= -50" Released. to: Unrestricted Use Building 27 Open Land Area S.4 S 0,ý ! \\

S o 0 2 1 1'. 1 " '1: '20 ,'11 22 23 2-' 2b2, 272......' W N Figure 4 : TFF Utility Corridor Grid Map s E 63 3 4 5 66'6 ' 4t1 48,128384858 85 5 '4,. r ,'.i -. 82

i. 8[

iO 8 g 9 CC EF I0 LL M NN 00 Y p, E~l RR GG TJ \\K, LL* MM NN 00 pp 99 RR" Ds ETT Asphalt '.(4" 70: SoilA/Vgetation:00 Soil/Vegetation 00 Soil/Vegetion

Asphalti, 3p

ýý -- ..................... a i........... S........\\- I. "AAsphplt 792' Asphaltlt 7, 7 71-4 TFF UTILITY CORRIDOR FOOTPRINT A .4. -A

q' S.

.4 .4 q* .4 .4 '3,. Cr, ."I. Concre Pad A S *'C....* "-A v-I K P m 7 C 7-, ?': ";7 )(*)

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,[.:

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.4 .4 .. 4 F UTILITY CORRIDOR FOOTPRINT )halt .*.... 1 iAsphalt : A---h --- Hot& CII Storage Area I, I. .4. '4 '(35 '.1' '4 791

*.4 7*2 4

"..4 = " 4.. / TF .. 4 V .i Asp

SW N Figure 5: TFF Utility Corridor Area: Locations and Results of Fixed Alpha Measurements s S 5 8 10 11 12 !2 14i1516 17 18.19 20 21 22:23 24 25 26:27 282 30c) ! 32033 32 35336 37 38"3(7 3 48 0 41 4234344 445 '4317 41)9 40 1 4"4 444. 50,7 6 4-6081 3-4 8C 7255 7666970: 776 7!, 78 79 80 51 82:83 S..... o o. .16 3 6 6 5 6.'7 6 9 0 7 2 7 4, : 7 7 7 8 9 8 0 1 8 2 8 8 4 5 8 6 7 8 8 9 9 A CE7,), ý Fp G ,-.5.%- 14 6;,): [i;: 2 0;' 4.... IH <2 K47 L '<20 jm Concrete<2 -'A 7,.17.74,4517-. 0-.. <20.. / /--"-,._ R U 0."

TFF UTILITY CORRIDOR BOUNDARY vv 75:.:.7i

/ 0

1... -k*

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<20...* $1 779 7,5

....2..0.................-4---

LL 20<2 <20 <20',<2 0, ,00 -<20<2 20, I`:, Jj P <20 <2020<k2<20 22"0" KKI ikR-

Figure 6: TFF Utility Corridor Area: Alpha Scan Survey S3 0 011123 14.15 1, 17,139 2021 2223 2 425 2'26 28 292031 323.3233 3.A 73 49 4-4214

,A.l 45.4,34-.7 44 S

3.

5556 b5 9 50,-)1 6.263 64 65 C 67 '6970>'T 72173 757677 7 9 081 82 83 84 85 8`3' 878,8990 A E G H L m M N 0 F' Q R U V x Y AA BB CC 7'" -¢.!* 7*;

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8.

".B L..* A i... Mý)3 7 - Hot &Yl Slorage Area F 7791 77;2 )RRIDOR FOOTPRINT N N S

{*

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nr 9.91 RR ss TT I

7.,11

,1 7.4 to maximum readings = 0 - 20 cpm to maximum readings = 7-25 cpm to maximum readings = 18 - 40 cpm 2.,"

73.ý

V N Figure 7: TFF Utility Corridor - Fixed Beta Survey Results in dpm/1 00cm2 E 2 3 4 5 6 7 8 a 0) 1 102: " 4 2531,1. 18 !19 2021 22.23 24 25 25i26282930 3 !32 3.3 24 .1 ',G 3 "f40 4246324

46. 45 17 465 66:5, 2 5 550-50.1 6'61 6

72 73 74 7 75 ;76 /79 8081 F2 83 84 8 A S* 5 '"5; /* I107 S.. .........0 54 4 o

'41 H

~~~~705 1.050.. 0 1100 S...

4..*

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784, T1>"GA............................................................

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/i\\

i 7FF UTILITY CORRIDOR F"OOTPRINT. x

(

92 68 ; "" J: I

643 714 963 419 664 9

z 1 1,0 4 5 7 7 -- 2: AA 77)": 7, 7!" -,-n\\--- (*!7 ln* ) B*~~~~- ....*,...* *,J :.................*......---. 59-63177 74 DD 75X 1 726 18i 900\\\\ 1 I I680 ,,i25

s'!i" 996::

ii*\\Y i ot I/ lot*rage Aroai .......... k. oc7,.7.. i -.*/!i P 09 570 55: 7 0 950 7 1 6, 4 165 -i - - -i K/ LL 917FF191L1187751OR7OOTPRNT763 T T ./)...

Figure 8: TFF Utility Corridor Area. 100% Beta Scans/Survey Results in cpm 434cm 2 (background not subtracted) "1 4 5 6 7 8 9 10:11 12

1314:1516 17
"09 21 220 232 25 25:27?28 29i' 0*I
132 3 -1".r-,4 7

41 4 4 4' 74--'., 3733. 5 -1 el4 16 7 4 4 60 6! 2 63 6-165 / 7 68869 70'71" -k

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Fl N 0 U Q x Y AA cc K I I U tI.LI I I Y rFt-I.JJII-UU I t-/?IlVNI 9' 4. ,'5 ' E. F A ~~1700-26004 1700-2600)ý 1750-2300)-* 1600-1900 Pad

- 1950-2400~

1800-2300 A. ..... / --/

.........4...........

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/~~1750.2100

/I(t 712 O 2000-2400 ~2000-2600 4 .2 0 1800-22 .1 -2 00 850-2350 --. 62002450 -,--- 950-2400 900-235 -1900-5000-2... 1020 -2704 002..................... 0001 41.00-2400.. 1650-245000A 2400-26001800222400-2600002002300-2800ý 2185022350 2000026000 24T041800019 /4_ 850 *0._i,2 _ I i \\ ii ._.,.-:' \\

i --.

41900-2100 1900-21oo0 16oo-22oo0 oo:* r -0 S........ 0 -2 00, -(-2*- I \\ [ * \\1 3 00-2 800. 23 00-28 00 o 424 00-2 6 00, '4 3 00 2 7 00 18 00 19goo,,24 00 2 6 00 ; 24 00 2 6 0 )* 3 - 8 / 7 2 6 1700-2300 ".2400-2700. .2100-2400. 0-2400.2400-2600 "..2400-2700"-.2300-2900--- 4 1 TPP: I tIT IITV r p ln j; F:rf -ri'~ w. 7.' 73 74 75 76 77 78179 A........ .5'. 7.4 V.. CORRIDOR 80 81 82.83 84 85 8I 87 88 89 90 T *.,

rt
r6

4.

0 5 0-2600 "2200-2600 "2300-2600. 2300-2500 "2100-2500.:142500-2600 bK2100-2600, 0-'2500."L22 *,6 00.d.2400_2500 : \\ HotCell S*orag Area Y -,.... :... ,'\\: >-"...

.....t,.

i \\' \\: \\: /

0

.7T9 7791 2;:'(i ";" s' 4.......... -I N '1 2, 5........... A V C DI .w N - Z)3 TFF UTILITY II KK LL N N Ppp TR ss T T FbOTPRINT .74.. II1" II I I IIII[

Ii* I I n r "it3 N

W 5 1 1

SW N Figure 9: TFF Utility Corridor Area: Fixed Exposure Rate Measurement Survey Results in VtR/hr at 1 meter s E 12 3 4 5' 6 7 8 9 10 11 12 1 14:1516 17818 92021 22:23 242526 27282930 31 3233344 53637 3 9.6 40 4-' 4:44 454647 4849 50-15 53554 55565?7E8,59560 61 62636.6566676866 7017 73 74.75 7677 7879808182:8384 8 A .C ...of )3 ~ ~. ...3. -r D 7-5 r... z-- 6i7 17 17.17 18 1 8 18: 18

18. 18 4.............................

C n r t 1

81 9 ':1 8 1 8 1 5 1 4, 1 3 1 3 1 3. 13 '4 4:

Pad, "N

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i.18 16 5 ,"o 12 12 12'12 72.....75556"75 6,, ';"/u

62J

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626 6#,

'¢4

?** P 818718 17:17161)'12:1212 13:13:1212 13 14:1515 15 1 7:18 18 18 17:1 16 4 12:12 12 13 13.12 12 12 14:15 15 15 15 15 '7 / 718 18 18 17: 7

~~

212 12 13 13:12 12 12 13:15 151.71 1

7 7 15 14 127 12 12 13 13-Tf3 13 13 13-745 15 15 17.--;!l"21 20 2 k

T 19.181 ..141313.12:12.12.12 13.14 14 1414:14*15'1517 0202020:20171. LU.7:1 7 1 1 71 9 1 9'14 13 71 7 : 12 12 2 1 3 : 4 1 414.]

1

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5.

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1.

2 0. ..*2. 1 7. 1 7. 7

1.

2 0. U7 1919 7:141313 13:121212 13:14 14 14 14:14 15 1 19:20220

1616"71:171 TFF UTILQTY CORRIDOR BOUNDARY jj' 1, rq8-1 11T:.1 A13 13 134I313 131la.14 14 14 15 '5 91.ý 20 157 17 16 16,P,16 16 16 1 20' 20;420l "h

'18:1919171514 131313:1"3131414 14: 1 5

1 19918:19 1 1716:1716 1616:1617171:8 17

8.

232320:1717 17 17:17 17 1717:18 18 18 18:19"191919:19191919:19191919:19 191919:19191919 AF 1* '7 18:19 19 13 1313:13 1361414:14 1415 19 18 19 19: 66 16 16 1616 1

18 187 2323 17-17 17 17:17 17 17 17,17 17 18 1818919 19 19 19:1919 19 19:19 19 191 715 :1413 13 13 3131515 14 1 9 :191 8 1

1:17917 1717:17 17 171717 17 178

18 181 9 19:1 18 19 19:19i 1919 19:19 19 19 1919 191919,

AA 1'7 17 18:19 1917 15:15 15 15 1 3'l 1 15 17 :14 18 19 19 18 19 181 7 1 6:71861816816 18 18 17 20 1 22 22,

21 176 7 1717 17 17 17:1i7 17 17 18-18 1 18 19:1I7 18 19 19:19 19 19 19:19 19 19 AA..

8-17817 17 718819

171 81 81 9 8 8

18 18

1 8 1 1 : 8 8 1 1 : 8 8 1 : 8 8 1 1 : 881 1

1 7 171 18 18P18 818 1717:17 1*11 1:17 17 17 17: 17 19 T1 9 I CO-R9D9 R B OUNDARY "9. 7 ' 7 1.......... A ---...- 1-7--,,..... --... BB, 8 19: 18 1717 1

18 18 18 1 1918 1:18 18 8

18 18 18 1 8:18 18 18 18:18 18 18 18:18515 18 1899

9 7

7 17: 17 17 17

17 CC 8:818 7'7}7

7 1'9 1199:18 1 88188 18* 18'18 811"7171 81 8181 7;

{>* I' CORRIDOR BOUND R cc8

19 818 1717:17 1 8 1 1 917:19 19 1919:18 17 71 1414 1717 4141 1717i178i7 14 l lil:

71 81 4: 1 4 18 17 1 4:171 r718 18 1 020 2O:f7 0 17'{7 17 17...:17.. Z-1 '6 .D 9 18119:18 18 17 17:18 18 182188161581414141414:14 Z14 :1414144 14 714 4 1 4 4 4 45 5 5 4 11 15:17 r a 9 1 9 1 9 2 .:1 1, 1 141 31 1 131 12 12 45-13:12 13 1313:13 14.:rl71 91V

6- -ý7171 71 7

91919... 19019".. T18 1819 4 2020 16 1513131314: 4114:4 15 15. 14r 14 311451144 124125 14212 413:413 914 :201 4 1421 1 8:*202 2121821 21 21212 20 2 20 1.-"-f71.. ~~~... .O.2.2.'. .0.. .l.. .7.1.1........... .,,r F., 18 18 18 18

18.1818 18 18 :

15 152 2 151 616 15 -16: 1 91 94 14 1 9 94 14 14 1 74 18 18 18:18 8 1 7 9 9 119: 020 20 20:12-2 21:2221-4142014.14.14204.:20 15..... S. .4 .4

L.

G 9 191918:8191818112020201* 6

91140, 2414:141441

1 21.914 1

9

19191919:194199901 129219:1919:191919 20:19 21 1017:12

.-Ok LL 189 1919 19. 1 9:19191

18 18'18520:2020 14 15 :1 9214 141*: 200*3 1:

2 20:20 2 0 20: 19 313:12 12 12 13:12 13 13 13:13 14 1

.20 920 20 20:20 20 20 20:20 20 19 19:22 2220',

7 M 18 1819 192019 :18 1819 1 20:20415 15 12 00140 4 14:14 14 142 1.-A- "14" 122 2022:1220 19 12 912 0 2102 21:213213 0 1 82020 12 18 :20 20 20 .2

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121 02:30 II 1819 :::T919 20 19 'B 8 9 2 7214 14 14.

4 "4" "

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i)a,,

a,<;;,4;,

18 18 18 18 01 618 6 8182 191:19 918 117 18 18 18218 18 18 17:19290 9 19 19020 O202020:21 21 21 21 :22 21 20 20'.. KK 18 19 19 19 19 19:19 19 18 158 1515 69 02 202 10 11 19: 9 1 2 19'19 19 19 19 19 19 19 19.19 19 19 19020 20 20 20:21 21 21 21021 20 20 20: " 0 818.19 19 19 19 19199191 51181918 18191:1 20 920:1220 20 2:19:20 1919 20:19 19 20 20:20 20 2020:20 20 20 21,2020 20 2020 19 20 MM 'I8

1. :9.1.9.1.1

..9..lll.o20 0 '1 0 19 21';9 200 200 2U7220 21 20 210"i,20 20 20-,f9 0 1 fd'0 20 20 2(0*2f21 21.... 20' 6'.'.".....0 20...

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S1 8* 1 "8 1 9 " 8 ! I ' *1 1 9 1 1 9 - I '41

1.

182 2 16 1 16 1 18:9-1,18o9:1 1818 1 :2020 9 1919-8 1 18 20 20 20 20:20 20 20.20:20 20 220 20

20 20 20 20'ý 20 20 20: 19 1 C 18 1.91 191 : 9.191 191 18 9:18 187919:18+9 19 2 :20119 20 1 :1,19 9 920 1 2{2 21 21 2112.

PP 17 17817 17 18 17:19189 18i8919 18 19:18 18 19 19:18 19 19 20'20 219200 19:192019 2023 232 1 1 19 T FIF8" 1 N ss TFF UTILITY CORRIDOFR BOUND'ARY TT '< /

iwo L. N-o*, him bo o-l.. i ~o-biol n....'in-" Z -<<-n 0," f t

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W N Figure 11: TFF Utility Corridor Area, Soil Sample Locations 0 E 4 " 8 T 1"12 13 14:15 16 17 18:19 2021 222-; 24 2526:2(, 28 29 30:3132331 3,41"7:';r 38.39-11 41 ii'4't .1 46:475.19 50 'w 'K 'r.1 56 57 (Kr5q 60.61962-1364 4 5 47 69 72 L -,5

r*

67 68 6970 ,11 72 7-,74 75 76 7 -, 79 9 0 hl 82 '83 84-858.1; 8 7 88 990 .1. 7,* L I Y 7 R .I' U IV ,*,AA 00 cc DD EFE HH KK L.L. RR lTss K @ = Soil Samples (top 0-6") Kf 1'* - .4 751 '4 1.

,(,

(:,1h 775'1 '4*; -41, E." F H" I mConcrete J, ,,5.7 A4D 7., a W 0 7........ 0 i" 7' 0'd* 7 5 7 2 7 5 7 1 7 5 '* 77,119 3. S.... ,'f '......IL 7 07fb 77-. .7J7 7..... I~ o o /:. "'- 17 /... .. 1 /....*..... I *. "" .'.- '. I....... ': ~~~~~~~~~~ ~ ~

t

.: 7.....,.,

~ ~

~ ~ ~ F UTILITY CORRIDOR v..,... FO..O... T.P.RINT.. 76-.4 4ol Coll Slotage Area ,7 7 7VT,, -4.......... .711 ? '.14

7' 1

I I >ir4 .7 1 A El C il 4. FOOTPRINT x I x I L/ I X. I \\-j \\-/ 1 r - n1tv I f[ r" *Ud r t I L I i*4 vv q "7"" - -.q -.

Figure 11A: TFF Utility Corridor Area 3: Soil Sample Locations. All Soil Sample #'s Begins with CORR-S (soil)-YY (year)-00 (count) E 10 11 14 1 14 15 16 17 18 19 12 2 0 2 2 3 2 4 2 5 2 6 2 8 9 33 1 3 2 3 3 3 4

3 5 3 6

,3 7; 3, 3 9., r 3 --...- ,,,-4 .4,4 5.64 74 S.................. i.... BB 74c ID JE FF JH "197 \\ \\: (170 (183ý 185 199 (208 (182: (181) (165) 4..::i 18 (164') (172 (1 79 (178) (1776176 130 (31> 132) (33") K. 14-140, 139 (38 (1' 1 3

6) !

(ýl354 ri42* (1{43 "1 4"*/"'/5 (1 *46)

(147')"(*148")

(.1"4 ý 1 \\...50..... 54 l 5 52 (15 1 78( 1 8 9 0 l 57 5-1 5 1 87 1 8)189 190) 19 .L-S........ "1, I

~~~~~~ ~ ~ ~ ~ ~ ~ ~ ~ Figure 11B: TFF Utility Corridor Area 2: Soil Sample Locations. E All Soil Sample #'s Begins with CORR-S (soil)-YY (year)-00 (6ount) 30 3 32 33 34 T U v w 103 y

15) 114ý z

(1725)

AA 17 .4.-. 35 37 38 39 40 41 42 (983 43 44 45 (v?) /' 101" 1 1 2 ( 124) 111.. 8I 116 (ioo 105 N.

7 110 (117 C123 (122)

I. I. 11....0 o09 !.!.................................I / (108 " -/ i18 (121 ' (128~) .4 .1:%\\ .o o \\ BB

12 M N Figure 11C: TFF All Soil Sample #'s 13 14 15 16 17 18 19 20 '*2 3) Ný N / Utility Corridor Area 1: Soil:Sample Locations. Begins with CORR-S (soil)-YY (year)-00 (count) /' .5) 24 25 26 27 28 29 30 3 W4N 4*** N N '48 20 ("9 ' "10 (11* (19 N .1 / 1<18 (19") (, 8"17 (16 5 .i5 14) / 21' 36' (22) (35) 23 ,24 1) 34 (32') (2K) (31) (30) 0 S (52) 54)

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General Atomic's Final Radiological Survey Report For TFF Utility Corridor Appendix A Final Survey Plan

Page 1 of 5 April 8, 2000 Prepared by: W.LaBonte Approved by: W Date: goo 3-O*-QO ( Final Survey Plan for TFF Service Corridor Asphalt and soil surfaces ONLY This survey plan is for a strip of land that may be excavated to install service lines, (water, sewage, power, fuel lines), to the TFF, Building 22. This piece of land extends from the TFF footprint to the main access road (portions of which had been previously released), in a Northeast to Southwest direction, and from the Linac footprint to the parking lot West of the Temporary Soil Staging Area in a West to East direction. See Figure I for details. This survey plan is for surface scans of asphalt and surface scans and samples of exposed soil surfaces only. Another Final Survey Plan, for soil under asphalt, will have to be developed when the exact location and depth of the excavations for the service corridor is known. This piece of land encompasses Unaffected Areas and Non-Suspect Affected Areas. See Figure 2 for classification. This survey plan is for land areas only. Some of the land areas are paved with asphalt. The Hot Cell Trailer Facility is within this foot print. It will be excluded from this survey plan until definite plans on the disposition of the Trailer are determined due to the difficulties in surveying under the trailer. This land area is approximately 2650 mi. Background and Classification Background Information This land is the access to buildings in which the majority of nuclear related work at GA occurred, LINAC, TRIGA Reactors, Radiochemistry, the Hot Cell, and TFF. Portions of this land area is within the Controlled Areas for these Buildings. Characterization, Post Decontamination and Final surveys conducted in the buildings adjacent to this land area indicated each building had it's own unique radioisotope mix. Noting that there is a possibility, if cross contamination to this land area from the buildings occurred, that the predominate isotopes from each of the adjacent buildings are a possibility. The release criteria selected is based on the most restrictive isotope for each type of sample/survey. See Release tff service corridor fsp.wpd

Page 2 of 5 Criteria, below, for details. Classification The classification of this land area is mixed. It ranges from Unaffected Area to Non-Suspect Affected Area depending on it's proximity to buildings in which work with radioactive materials occurred, whether it was inside or outside of a Controlled Area, and Final Surveys in Suspect Affected Areas immediately surrounding the Hot Cell and TFF facilities found no radioactive contamination above release limits. See Figure 2 for details on classification. Survey Objectives and Responsibility The purpose of performing a final survey is to demonstrate that the radiological conditions satisfy the NRC and State of California 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) does not exceed three times the average value in an area up to 100 cm 2, (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 ýIR/hr above background measured at 1 meter above the surface. Samples will be taken 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 (per GA Site Decommissioning Plan) Direct Surface Scans Characterization surveys performed in the adjacent building included gamma spectroscopy analysis and 9`Sr analysis (performed by a contracted laboratory). The predominate isotopes detected depended on the building's use. The predominate beta/gamma emitting isotopes were '37Cs, 6°Co, and, at the Hot Cell Site, 90Sr was detected on 1/2 of the samples sent for analysis. When 'Sr was detected, the 9"Sr to '37Cs ratio was 2. 1: 1. At TFF, enriched uranium was the predominate radioactive contaminate. The applicable release criteria for beta/gamma, based on the Hot Cell site mix, are: 3,000 dpm/100 cm2, averaged over I m2 area 9,000 dpm/100 cm', maximum in a 100 cm2 area 600 dpm/100 cm 2 removable contamination tff service corridor fsp.wpd

Page 3 of 5 Alpha contamination was detected at some of the buildings adjacent to this land area. The alpha release criteria for direct scans of surfaces are: 5,000 dpm/100 cm 2, averaged over 1 m' area 15,000 dpm/100 cm', maximum in a 100 cm2 area 1,000 dpm/100 cm 2, removable contamination. Exposure Rate Measurements The guideline value for exposure rates measured at I m above the surface is 10 [LR/hr above background. Soil Criteria (soil limits apply to roof gravel, concrete rubble and asphalt rubble) The release criteria for soil are specified in the Site Decommissioning Plan and summarized below. The values presented below are above background levels. Note: Soil, asphalt and concrete rubble must remain on-site until specific approval to move it off-site is granted by the NRC and the State of California. 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. If other nuclides are encountered, notify HP Management for release criteria. Gross alpha/beta results are required in addition to gamma spectroscopy analysis for a representative number of soil samples (to have an upper bound for the maximum Sr-90 which could be in the soil). Sr-90 analysis may also be required if gross alpha/beta results indicates Sr-90 may be present. Alert Levels If the following "alert levels" are exceeded, notify HP Management so an evaluation can be performed to determine if increased survey coverage or decontamination is required. On Concrete or Asphalt Surfaces Note: The Alert levels provided below are based on the background cpm plus the meter cpm value taking into account the instrument efficiency and probe surface area. The alert level tff service corridor fsp.wpd

Page 4 of 5 for each instrument used must be determined prior to performing surveys. The background determination must be performed in building 13 or other HP management approved area. Alpha Monitoring >100 cpm alpha using the large area (434 cm 2) probe. If >100 cpm, check with a hand held alpha meter. >60 cpm using a hand held alpha probe, notify Health Physics Management. Beta Scanning using 434 cm' probe > -500 cpm above background using any other 434 cm2 probe Beta Scanning using a 100 cm' detector > - 200 cpm above background Beta Scanning using a 15 cm2 pancake GM detector > - 80 cpm above background. Exposure Rate Measurement Exposure rate measurements at contact ( 1-2" above the surface) and at I m above the surface: 20 [tRihr. Soil, Gravel, Asphalt Rubble, Concrete Rubble Samples Any Radionuclide above natural background levels (see HP-40 for background levels). All soil sample results must be reviewed by Laura Gonzales, Paul Maschka, or Bill LaBonte. Site Conditions at Time of Final Survey The following is the status of the buildings adjacent to this land area at the time of this Final Survey Plan: Building 22, TFF The Building has been release for unrestricted use by the NRC and the State of California. A Final Survey for the land surrounding this facility has been completed. The report is being prepared. tff service corridor fsp.wpd

Page 5 of 5 Building 23, Hot Cell Facility The building has been dismantled, the Final Survey on the land area was completed, Confirmatory surveys were performed by the NRC and ORISE. Building 21, TRIGA This facility is in the process of decommissioning. Building 27, Radiochemistry This building has been released by the State of California for unrestricted used. Final Surveys on the land immediately surrounding this facility have been completed. Confirmatory surveys by the State have been completed. Building 27-1, EA-I Bunker The Building has been demolished, (except for I wall which is used as a retaining wall for Building 27), and final surveys on the land area are in progress. Final Survey Reguirements The minimum survey requirements for this final survey are outlined in Table-I, Planned Surveys for the TFF Service Corridor. The minimum number of soil samples and locations in the UNAFFECTED AREA is identified in Figure 3. The minimum number of soil samples and locations in the NON-SUSPECT AFFECTED AREA is identified in Figure 4. 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, efficiency, background readings (if applicable) and any other applicable information. tff service corridor fsp.wpd

Table 1: TFF Service Corridor Minimum Final Survey Requirements Area Surface Dose Rate Fixed Measurements Soil Samples Contamination Measurements (fixed a or P or swipes) Unaffected Scan 10% of area with a At a minimum, take At a minimum, take At a minimum, take surface 434 cm 2 dose rate reading at I fixed readings for ix, P3, soil samples at locations a and P3 probe at 1-2" meter from the surface or swipe activity at each indicated on Figure 3 at 0-6" from surface at the center of each location identified on deep. Take 4 soil samples full 2 m grid using a Figure 5 for a total of 14 Nal detector for a total u, 17 P3 readings and 13 of 394 readings. Swipes. (Requirement: 1 (Requirement: measurement every 7m) 1 reading every 3 m) Non-Suspect Scan 100% of the area At a minimum, take At a minimum, take At a minimum, take surface Affected with a 434 cm 2 P3 probe dose rate reading at I fixed readings for a and soil samples at locations and 10% of area with a meter from the surface P3 activity at each indicated on Figure 4 at 0-6" 434 cm 2 Ca probe at 1-2" at the center of each location identified on deep. Take 63 soil samples. from surface full 2m grid with a NaI Figure 5 for a total of detector for a total of 50 c, 49 P3 readings and 925 readings. 47 Swipes. (Requirement: (Requirement: 1 reading every 3 m) 1 measurement every 1 _4.5 m)

Figure 1: TFF Service Corridor Af ED 7 p S ) _______-\\ = Unaffected Area = Non-Suspect Affected Area = Not inclueded in TFF ComdolFServmce Temporary Storage Area 0.93rm = lore S..... ' *" / / V '. Hot Cell Site OF,

Figure 2: TFF Service Corridor Classification 4, P.S 'S E. Bw/d~ra Hot Cell Site .7 I, -.7 = Unaffected Area r - Not inclueded n TFF Corndloarervice Temporary Storage Area 0 93cm = torn 7>"'~~.A </' '4'w%74Ž' 'N ,Ž'K'/Ž':::.,; / <:"'>'7 .,,.., - -......,..-.../ / i

Figure 3: TFF Service Corridor Unaffected Area Soil Sample Locations V Bilding tUnaffected Area = Nor-Suspect Affected Area ______= ,Not riclueded in TFF CorndoCService "' SoW Sample Locaions Temporary Storage Area 0 93cm = 1Om 1.* ID Hot Cell Site '9 <1 2-/... N

Figure 4: TFF Service Corridor Non-Suspect Affected Area Soil Sample Locations t Hot Cell Site ,A

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Figure 5: TFF Service Corridor Area: Exposure Rate Measurement, Alpha/Beta Fixed Measurements and Removable Contamination Survey Locations 1 2 3 4 5 67 8 91011 1213i141516 1718:19 2021!22123:24i25 262728 29,30131 32.33:34 35,36 37:38!3940 41 424344 4554 646566876869i70.71 72;73 74 75'76 77:7879ý80181 8283184i85186:87 8889:90 4 A F S........ G H: o,... 117 u ~~~... K L (*I ~ ~~~ ~~ N'

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General Atomic's Final Radiological Survey For TFF Utility Corridor Appendix B Confirmatory Survey

Appendix B TFF Utility Corridor GA Confirmatory Survey Description Following the completion of the TFF Utility Corridor Final Survey, a Confirmatory Survey was performed by a Health Physics Technician, not associated with the Final Survey, in accordance with an approved Survey Plan (attached). The purpose of this survey was to confirm that the Final Survey was effective in identifying the radiological conditions of the area. This confirmatory survey consisted of:

1.

17 soil samples which ranged from Not Detectable to 0.96 +/- 0.15 pCi/g, 1 7Cs, and from Not Detectable to 0.24 +/- 0.12 pCi/g, 6"Co. See Table 1 for results and Figure-2 for locations.

2.

Exposure rate measurements at contact and Imeter from the surface at 36 locations. Theses ranged from 15 to 24,tR/hr at contact and 15 to 25 [tR/hr at 1 meter from the surface. The background ranged from 18 to 22 [tR/hr. See Figure 3 for locations and results.

3.

30 swipe samples for loose surface contamination which were < 10 pCi/100 cm 2 alpha, and a high of 14.46 pCi/100 cm' beta activity. See Figure 3 for locations and Table 2 for results.

4.

22 fixed alpha readings, all of which were <20cpm (background). See Figure 1 for locations and results.

5.

30 fixed beta readin2s the range was from <MDA to 1416 dpm/100 cm2. See Figure-I for locations and results.

6.

100% of (30) 2mx2m grids were scanned for beta activity. The range was 1600 to 2400 cpm using a 434 cm2 proportional detector. The nominal background on asphalt for this detector is 2175 to 2460 cpm. See Figure I for locations and results. Conclusion All of the Confirmatory Survey results indicated that activity levels on the TFF Utility Corridor open land areas are below the approved release criteria, which agrees with the Final Survey results.

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Table-i: TFF Utility Corridor Confirmatory Survey Soil Sample Results Radionuclide Concentrations (pCi/g) Bo( k-rowid A!.Subtracted U-238 U-235 (s-137 Co-60 Th-228 Th-232 (63 Key) (144,186 Kcv) (662 Key) 1170+1330)/21 Key (238 Key) (911 Key) p:# I'vel

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t.... I pCi/g pCi/ +/-.. p('i/g / ,pCi/g v, I C M pCi/g A error pCi/g error pCi/)- error pCi/g error pCi/g error p('i/g CerOr pCi/g 20 20 20 20 20 20 I UL -I (0.97 101.5 0.98 0.12

88)

(I0.1 024 44.3 0.11 0.13 61.6 0.08 0.71 19.0 0 13 1.30 24.8 0.32 2 UC-2 2.02 51.0 1.03 0.19 5935 0.II 0.12 53.4 0.06 N) 0.00 0.90 11.6 O)10 1.27 25.4 0.32 3 DIC-3 NI) 0.00 0.111 107.1

0. 1 1 0.16 53.6 0.09 ND 0.00 0.75 13.3 0.10 1.37 26.1 0.36 4

UC-4 NI) 0.001 0.12 99.6 0.12 NI 1 0.00 NI) 0.00 0.90 21.9 0.19 1.51) 23.3 0.35 5 UC-5 ND 0.00 NI) 11.00 0.10 66.0 0.17 NI) 0.01 1.96 11.I (1H1 1.74 19.5 0.34 6 1C-6 1.34 78.9 1.06 0.17 49.0 0.08 NI) 0.00 ND 0.00 1.08 11.6 0.13 2.06 17.1 0.35 7 UC-7 ND 0.00 0.16 56.4 0)09 NI) 0.00 NND 0.00 0.99 10.1 0.10) 1.35 28.9 0.39 8 UC-8 1.76 698 1.23 0.14 60.11 0.08 NI) 0.00 ND 10.00 0.70 17,8 0.12 1.17 27.3 0.32 9 UC-9 ND 0.00 0.11 64.7 0.07 NDI 0.00 NI) 0.00 0.97 12.3 0.12 1.74 19.7 0.34 10 UC-10 I 12 96.7 1.08 0.09 63.4 0.06 0.1t0 79.2 0.18 ND 0.00 ).73 15.9 0.12 1.39 24.4 0.34 II UC II 1.68 71.4 1.20 0.16 41.4 (.07 ND 0.00 ND 0.00 1.07 9.8 0.10 1.56 22.6 035 12 UC-12 NI) 0.00 0.13 78.1 0.10 0.12 60.0 0.07 0.I10 62.8 0(.06 0.88 11.7 0.10 1.38 21.0 0.29 13 UC-13 ND 0.00 0.16

53. I 0.09 0.09 97.4 0.09 0.24 47.9 0.12 0.90 13.4 0.12 1.68 22.5 0.38 14 UC-14 1.79 61.7 1.10 0.15 59.0 0.09 0.40 22.8 0.09 0.08 88.5 0.07 1.39 8.5 0.12 1.97 19A 0.38 15 UC-15 0.95 96.2 0.91 0.13 62.2 0.08 0.30 34.6 0.10 NI) 0.00 0.91 12.6 0.11 1.64 18.6 0.31 16 UC-16 ND 0.00 0.13 73.0 0.09 0.54 20.2 0.11 0.07 115.9 0.08 1.38 9.4 0.13 1.75 214 037 17 DC 17 ND 0.00 ND (1.010 0.96 16.0 0.1 N D 0.00 0.74 24.1 0.18 1.56 23.7 037 Note: ND means not detected.<O. 1 pCi/g Cs-137, <0.1 pCi/g Co-60, <3.0 pCi/g U-238, <0.3 pCi/g U-235 W

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Table 2: TFF Utility Corridor Confirmatory Swipe Survey Results Swipe Gross a in Gross P3 in Swipe Gross a in Gross P3 in No. dpn/100 cm2 dpm/100 cm2 No. dpm/IOO cM2 dpm/1000cm2 1 <10 <10 16 <10 <10 2 <10 <10 17 <10 <10 3 <10 <10 18 <10 <10 4 <10 <10 19 <10 <10 5 <10 <10 20 <10 <10 6 <10 <10 21 <10 <10 7 <10 <10 22 <10 <10 8 <10 <10 23 <10 14.46 9 <10 <10 24 <10 <10 10 <10 <10 25 <10 <10 11 <10 <10 26 <10 <10 12 <10 10.89 27 <!0 <10 13 <10 <10 28 <10 <10 14 <10 <10 29 <10 <10 15 <10 <10 30 <10 <10}}

ML010720048

Text

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Dear Ms. Adams and Mr. Wesley:

Enclosure:

Background

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