ML20203C317

Final Radiological Survey Performed at General Atomics Bldg 37

ML20203C317
Person / Time
Site:	07000734
Issue date:	01/29/1999
From:	Gonzales L, Maschka P, Joseph Turner GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20203C305	List: ML20203C302 ML20203C308 ML20203C317 ML20203C325
References
PROC-990129, NUDOCS 9902110354
Download: ML20203C317 (150)

Text

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FINAL RADIOLOGICAL SURVEY PERFORMED AT GENERAL ATOMICS' g

BUILDING 37 I

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Prepared By: John Turner, Paul Maschka, Laura Gonzales, Stephen Finchum, Richard Stowell, Efraim Ramirez I

Comelius Stanley & Barbara Lyons.

l January 29,1999 I

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Table of Contents l

INTRODUCTION............................................................... I SITE DESCRIPTION........................................................... 1 PREVIOUS ACTIVITIES (HISTORY OF USE)....................................... 2

,ll CRITERIA FOR RELEASE TO UNRESTRICTED USE................................ 3 Facilities and Equipment................................................... 3 Enriched Uranium......................................................... 3 lI Natural Thorium.......................................................... 4 l

Beta Guideline Values (thorium) within the High Bay Area........................ 5 Release Criteria for Soils and Roofing Material (i.e., tar & insulation)................ 5 Exposure Rate Guideline................................................... 6 INSTRUM ENTATION.......................................................... 6 l

BACKG ROUND MEAS UREMENTS............................................... 7 Background Measurements for Instruments / Detectors

...........................7 Backgmund Roofing Materials (i.e., tar & insulation) Concentrations................ 8 Background Soil Concentrations............................................. 8 Exposure Rate Background.................................................. 8 DECONTAMINATION ACTIVITIES............................................... 8 1

FINAL SURVEYS PERFORMED.................................................. 8 Objectives and Responsibilities............................................. 8 Classification of Areas...............

..................................9 Final Survey Plans

.......................................................10 Sample Preparation and Counting............................................ 10 Roo fing Material Samples.................................................. 1 1 Soil Sampl es............................................................ 1 1 S URVEY

SUMMARY

.......................................................... 1 1 RESULTS OF THE FINAL SURVEYS............................................ 1 1 Scanning............................................................... 1 1 Fixed Measurements.....................................................

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Removable Contamination Sarveys......................................... 12 Exposure Rate Measurements.............................................. 13 Roo fing Material Samples................................................ 13 Soil Sampl es............................................................ 13 CONCLUS I ON................................................................ 13 1

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Lht of Tables Table 1:

USNRC's Acceptable Surface Contamination Levels......................... T-1 Table 2:

State of CA Acceptable Surface Contamination Levels....................... T-2 Table 3:

List of Instruments................................................... T-3 Table 4:

Background Measurements (Obtained from Building 13)...................... T-7 Table 5:

Results of Final Surveys in Building 37.................................... T-9 Table 6:

Roofing Material Sample Results........................................ T-11 1

Table 7:

Soil Sample Results from Rooms 13 9 & 13 9A............................. T-14 Table 8:

Background Soil Sample Results....................................... T-15 List of Figures (unpared)

Figure 1:

Plan View ofGeneral Atomics Site Figure 2:

Building 37 in Relation to Surrounding Facilities Figure 3:

First Floor & South Concrete Footprint of Building 37 I

Figure 4:

Second Floor of Building 37 Figure 5:

North Side: Locations of Large Area Masslinn Wipes I

Figure 6:

North Side: Alpha / Beta Scans on Walls & Floor and Exposure Rate Measurements Figure 7:

North Side: Locations of Fixed Alpha Measurements on the Walls & Floor Figure 8:

North Side: Locations of Fixed Beta Measurements on the Walls & Floor Figure 9:

North Side: Removable Contamination Locations on the Walls & Floor Figure 10:

Hallway: Locations of Large Area Masslinn Wipes Figure 11:

Hallway: Alpha / Beta Scans & Removable Contamination Locations I

Figure 12:

Hallway: Location of Fixed Alpha Measurements on the Floor Figure 13:

Hallway: Location of Fixed Beta Measurements on the Floor I

Figure 14:

High Bay Area: Locations of Large Area Masslinn Wipes Figure 15:

High Bay Area & South Wall: Alpha / Beta Scans and Exposure Rate Measurements Figure 16:

High Bay Area & South Wall: Locations of Fixed Alpha Measurements on the Wall

& Floor Figure 17:

High Bay Area & South Wall: Locations of Fixed Beta Measurements on the Wall &

Floor Figure 18:

High Bay Area & South Wall: Removable Contamination Locations on the Wall &

Floor Figure 19:

Overhead: Removable Contamination Locations

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Northwest Overhead: Removable Contamination Locations l

Figure 21:

Rooms 110 & 112: Locations of Large Area Masslinn Wipes Figure 22:

Rooms 110 & 112: Beta Scans on Walls & Floors Figure 23:

Rooms 110 & 112: Locations of Fixed Beta Measurements on the Walls & Floors and Exposure Rate Measurements I

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Figure 24:

Rooms 110 & 112: Removable Contamination Locations on the Walls & Floors Figure 25:

South Concrete Footprint: Location of Large Area Masslinn Wipe l

Figure 26:

South Concrete Footprint: Alpha / Beta Scans and Exposure Rate Measurements Figure 27:

South Concrete Footprint: Locations of Fixed Alpha & Beta Measurements Figure 28:

South Concrete Footprint: Removable Contamination Locations Figure 29:

Roof: Sample Locations & Exposure Rate Measurements Figure 30:

Rooms 139 & 139A: Large Area Masslinn Wipes & Removable Contamination Locations and Exposure Rate Measurements Figure 31:

Rooms 139 & 139A: Alpha / Beta Scans on Walls & Floor Figure 32:

Rooms 139 & 139A (Excavation): Soil Sample Locations & Exposure Rate Measurements List of Anpendixes Appendix A: Addendum to the " Final Survey Plan for Building 37 (SVA-South)" " Bldg. 37-(SVA-South)-Roof Sampling / Surveying Plan" dated July 31,1998.

Appendix B: " Final Survey Plan for Building-37 (SVA-South)" dated July 15,1998.

I Appendix C: " Soil Sampling Plan for Building 37 - Rooms 139 and 139A" dated April 13,1998.

" Characterization and Final Survey Plan for Building 37 - Rooms 139 and 139A" dated March 12,1998.

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• !* summ mensues Building 37 Final Radiological Survey Report Introduction General Atomics (GA) is continuing its efforts directed at decontaminating, as appropriate, and I

obtaining the release to unrestricted use of selected facilities at General Atomics. GA has recently completed the Final Radiological Survey of the remaining (southern) portion of Building 37 (Sorrento Valley-A). The northern portion of Building 37, formerly called the "SVA Fuel Manufacturing Facility," was decommissioned between 1990-1995 (SVA Decommissioning Project). After NRC and State of California approval, the northern portion of the building was dismantled and the site and surrounding footprint area were subsequently released to unrestricted use.

GA is requesting both the Nuclear Regulatory Commission (NRC) and the State of California for the I

release of the remaining portion of Building 37 to unrestricted use.

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This report documents the results of extensive and comprehensive radiological measurements completed inside Building 37, on the roof of the building and on the outside south concrete

" footprint" of the building and demonstrates that these areas meet the approved criteria for release to j

unrestricted use. The total surface area to be released to unrestricted use is ~ 38300 ft2 (~ 3560 m ),

2 Site Description A plan view of the GA Site is shown in Figure 1. The location of Building 37 in relation to other I

facilities at GA's Sorrento Valley Site is shown in Figure 2. The first floor of Building 37 as it

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exists (current status) and the outside south concrete " footprint" to be released to unrestricted use is shown in Figure 3. The second floor of Building 37 as it exists (current status) is shown in Figure 4.

L roof %f the building is shown in Figure 29.

Building 37 has extemal dimensions of-243 ft x 155 ft (74 m x 47 m) and encompasses an area of I

~ 37665 ft2 (~ 3500 m ). The outside south concrete " footprint" has an area of ~ 635 ft:(~ 60 m ),

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The total surface area to be released to unrestricted use is ~ 38300 ft (~ 3560 m ),

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The second floor of the building encompasses an area of ~ 20500 ft (~ 1900 m ). The roof of the building has approximately the same external dimensions as the building itself(i.e., ~ 37665 ft or ~

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3500m),

The remaining southern portion of Building 37 is currently being used for non-radioactive work.

The "High Bay Area" within the building was previously used for the temporary storage of properly packaged low level radioactive waste from the SVA Decommissioning Project. In rooms 110 and 112, sealed sources were used by the TRIGA reactor division for calibration of nuclear I

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ll 4 " " " "'A W WCW Building 37 Final Radiological Survey Report instrumentation.

Building 37 is divided into a ground floor and a second floor. There is a large "high bay" area lg within the building which extends from the ground floor to the roof and divides the building into jg eastern and western portions. Work areas, service and utility areas as well as offices are located to the east and west of the high bay area.

l The building's floors are composed of approximately 8 inches of reinforced concrete slabs. The l

concrete floors may be covered with linoleum tile or carpet in the eastern and western portions within individual rooms / offices. Some of the exterior walls are composed of concrete tilt-up panel construction and are approximately 7 to 12 inches thick (i.e., south High Bay Area). Other exterior g

walls are composed of standard cormgated metal stock (i.e., north High Bay Area). The north High j

Bay Area wall is new. It was constructed after the previous wall was removed during the D&D performed on the northern half of the building. All exterior walls are attached to a structural sted j

framework and adjoin the edge / footings of the concrete floor. Interior walls may be composed of l5 gypsum wallboard, concrete, concrete block or metal.

1 The roof consists of ribbed steel decking overlaid with a layer of rigid insulation and then a layer of tar. The ribbed steel sheets span supporting roof trusses and purlins to which they are welded.

There were no HEPA ventilation units located on the roof.

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An outside area, south of the High Bay Area, was surveyed as part of the building's footprint 2

g (approximately 60 m of concrete surface). The north side area footprint was addressed during the 3

SVA Decommissioning Project. The sidewalk and landscaping in this northern area were constructed after the release of the north half of the building. The eastern and western exterior l

footprints of the building, as well as the land area beyond the extent of the south concrete i

" footprint," will be surveyed and sampled in the future and a Final Radiological Survey Report issued for that land area.

The building also contains a tunnel and a tunnel annex, both located beneath the eastern end of Building 37, these tunnels were used to store properly contained Special Nuclear Material (SNM).

The tunnel and its annex will be addressed in a separate but complementary Final Report.

J Previous Activities (History of Use)

!u The northe m portion of Building 37 was originally built for use as a Fuel Fabrication Facility and the southern portion of the building functioned as a Machine Shop and office space. The Fuel Fabrication Facility was decommissioned, dismantled and the associated land released to unrestricted use (SVA Decommissioning Project).

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$caummeaLAfrDASCE Building 37 Final Radiological Survey Report The machine shop equipment was removed from the southern portion of the building and this area i

remained vacant for some time.

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The only history of radioactive material usage within the building was the temporary storage of properly packaged low level radioactive waste material from the SVA Decommissioning Project, and the use of sealed sources (i.e., beta / gamma emitters such as Cs-137) in rooms 110 and 112 for l

I calibration of monitoring / control type nuclear instrumentation for the TRIG A reactor division. The Iow level radioactive waste was moved into the building for temporary storage only after surveys were conducted to demonstrate that exterior contamination levels on the containers were below the release criteria. Based on the previous history of work conducted in the northern portion of Building 37, the predominant radiological contaminants contained in the waste packages were enriched uranium (typically ~ 93% U-235) and natural thorium.

The remaining southern portion of the building is presently being used to house numerous I

experimental non-radioactive endeavors with associated support facilities (i.e., offices, mechanical and electrical shops, utilities, etc.).

l Criteria for Release to Unrestricted Use Facilities and Eauipment I

U.S. NRC's criterion for releasing facilities and equipment to unrestricted use is shown in Table 1.

The State of California's guidelines, "DHS Criteria for Release of Facilities and Equipment to Unrestricted Use," also known as "DECON-1," is shown in Table 2.

Rooms 110 and 112 previously contained sealed radioactive sources (i.e., beta / gamma emitters such as Cs-137) which were used to calibrate nuclear instrumentation for General Atomic's TRIGA reactors. These two rooms were surveyed for beta / gamma emissions to determine compliance with the release criteria. The release criterion for beta / gamma emitters is the same as for enriched uranium (U-235) below.

Enriched Uranium I

The approved guideline values for residual contamination for release to unrestricted use for U-235 are provided below; 2

2 5,000 dpm/100 cm (averaged over a 1 m area) 2 2

2 15,000 dpm/100 cm (maximum in a 100 cm area if the average over 1 m s met) 2 1000 dpm/100 cm (removable activity) in many cases, beta-gamma measurements provide a more accurate assessment of thorium and 3 of13 t

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• l*canamesmranses Building 37 Final Radiological Survey Report uranium contamination on most building surfaces, due to problems inherent in measuring alpha contamination on rough, porous and/or dusty surfaces. These surface conditions cause less attenuation / absorption of beta particles than alpha particles. Therefore, for radionuclides of decay series which emit both alpha and beta radiations, beta measurements usually provide a more accurate determination of surface activity than can be achieved by alpha measurements. However, the relationship of beta to alpha emissions must be considered when determining whether to use alpha or beta measurements for determining the surface activity for comparison with the guideline value.

Within the high bay area of Building 37, alpha surveys were used to determine compliance with the release criteria, although beta monitoring was performed (for thorium). Alpha measurements are satisfactory for the following reasons:

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In " highly" enriched uranium (uranium, properly packaged and stored, in this facility was typically - 93% enriched); alpha monitoring is the method of choice. At this enrichment, the U-234 activity present is increased significantly. The alpha to beta ratio is approximately 116:1.8 Because of this, alpha monitoring is the measurement of choice for enriched uranium.

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Alpha surveys are accurate if the surface is clean and free ofdust and debris. All floor surfaces were cleaned by vacuuming and/or masslinn swipes before scanning or fixed measurements were performed.

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It was GA's goal to decontaminate the building stmeture to levels < 1000 a dpm/100cm2 (thorium imit).

Natural Thorium The approved guideline values for residual contamination for release to unrestricted use for natural thorium are provided below:

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1,000 dpm/100 cm (averaged over a 1 m area) 2 2

2 3,000 dpm/100 cm (maximum in a 100 cm area if the average over 1 m is met) 2 200 dpm/100 cm (removable activity)

I As interpreted by the NRC, the average 1000 dpm/100 cm' and the maximum 3000 dpm/100 cm2 should apply to both alpha and beta measurements, independently, for surface contamination 3 From Table 5-4 in " Health Physics Manual of Good Practices for Uranium Facilities", prepared for DOE by Idaho National Engineering Laboratory, document EGG 2530, UC-41, dated June 1988.

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.l. - - mronnes Building 37 Final Radiological Survey Report involving natural thorium.2 Alpha measurements will be performed to detect < 1000 dpm/100 cm,

2 Thorium emits alpha radiation to beta radiation in a 1:0.67 ratio; therefore, the corresponding I

average and maximum beta guidelines were adjusted to be 670 dpmilC0 crn and 2000 dpm/100 cm,

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respectively, for beta monitoring.

Since the instmments cannot distinguish between uranium and thorium contamination, the most restrictive activity guideline was used to compare all direct measurements for beta activity.

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Beta Guideline Values (thorium) within the Hich Bay Area The modified guideline values for residual contamination for release to unrestricted use for natural thorium are provided below:

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670 dpm/100 cm p (averaged over a 1 m area) 2 2

2 2000 dpm/100 cm p (maximum in a 100 cm area if the average over 1 m s met) 2 200 dpm/100 cm p (removable activity)

Release Criteria for Soils and Roofine Material (i.e.. tar and insulation)

The release criterion is 10 pCi/g above background for natural thorium (Th-232 plus Th-228),35 pCi/g for depleted uranium and 30 pCi/g above background for enriched uranium (U-234 plus U-I 235).

I The following table presents the typical isotopic analysis of the enriched uranium utilized within the northern portion of Building 37 (formerly called the "SVA Fuel Manufacturing Facility"):

I AVERAGE SPECIFIC WEIGHTED NUCLIDE WEIGHT %

ACTIVITY ( Ci/g)

ACTIVITY (uCi/g)

U-234 0.98 6129.54 60.069 U-235 93.15 2.14 1.99 U-236 0.40 63.56 0.254 U-238 5.50 0.34 0.0187 TOTALS 100.03 62.33 Based on the above, the weighted activity ratio of U-234:U-235 is 30:1.

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2 " Interpretation of Thorium Surface Decontamination Limits," U.S. Nuclear Regulatory Commission, Febmary 9,1992.

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_---------------------------------------------------------m 4 - =" menses Building 37 Final Radiological Survey Report Radionuclide Concentration Limits from Option 1 NRC Policy Issue (SECY 81-576)

Radionuclide Concentration (pCi/g)*

Natural thorium (Th-232, Th-228) with daughters present and in equilibrium 10 Enriched uranium (soluble and insoluble)"

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If more than one radionuclide exists, the sum of the fractions of the concentrations will be calculated as follows:

I ts L,

s.s C, =

The average concentration of radionuclide i.

L, =

The maximum limit for f (pCi/g).

The sum of the fractions must be less than one in order to meet the release criteria.

The U-235 concentrations detennined by gamma spectroscopy will be used to ensure that concentrations of enriched uranium are below the @n a limit. The ratio of U-234 to U-235 is thirty to one (30:1) for the SVA facility.

Exoosure Rate Guideline

'Ihe guideline value for exposure rates measured at I m above the surface, is 10 R/hr above background levels.

Instrumentation I

A list ofinstmments used during the radiological surveys is shown in Table 3. The table includes:

(1) a description of the instmment, 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 instmments used were calibrated semiannually and after repair, except for exposure rate meters which were calibrated quarterly.

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.hamnusuuummuser Building 37 Final Radiological Survey Report Background Measurements Backcround Measurements for Instruments / Detectors I

Building 13 on GA's main site was used for conducting background measurements on instruments used for the final survey because: (1) there is no history involving radioactive materials or storage ofradioactive materials in Building 13, and (2) the various surfaces and construction materials found in Building 37 could also be found in Building 13.

I For the fixed background measurements, shown in Table 4, the mean and standard deviation for each 2

surface surveyed with the 100 cm gas flow proportional detector were calculated using equations 8-11 and 8-12 fmm the draft version of NUREG/CR-5849 as shown below:

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Equation (8-11) 1 /

I Equation (8-12) b1 IA-#M n-1 I

Minimum detectable activities (MDA's) for each type of surface (see Table 4), were calculated using equation (5-2) from the NUREG/CR-5849 as shown below:

Equation (5~2) 2.71 +4.65/B,xt 2

MDA=

(dpm/l00cm )

^

E txEu 100 Where:

I Ba= background rate (cpm) t = count time (min)

E = efficiency 2

A = area of the detector (cm )

I 3 Manual for Conaucinir, R:Selegical Surveys in Support of License Tennination (Draft for Comment),

NUREG/CR 5849, ORAU-92/C57, Oak Ridge Associated Univershies, June 1992.

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O rmuurm moners Building 37 Final Radiological Survey Report Backcround Roofine Material Concentrations of Concern Typical background concentrations measured by gamma spectroscopy on samples of roofing materials (tar and insulation) collected from three different locations on the GA site, in pCi/g (at 2 6)are:

U-238 2.31 pCi/g

• 4.68 I

U-235 0.27 pCi/g

• 0.32 Thorium (Total) 4.84 pCi/g

• 4.54 Backcround Soil Concentrations ofConcern 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 8 with the locations where I

these samples were taken.

Exoosure Rate Backcrod I

Typical exposure rate background for this site is about 15 R/hr measured at I m from the surface.

This value can be measured south of Building 15 (an office building on the eastern portion of the GA i

site). Measurements taken offsite in 10 different locations over a period of a year also give an average of about 15 R/hr (measured at I m fmm the surface). Normal background exposure rates increase to about 22 R/hr at I m from the surface in small rooms with concrete floors and walls and up to 28 R/hr inside concrete lined trenches or concrete lined pits (background measurements inside a concrete pit near Building 2 confinned this).

Decontamination Activities Floor surfaces were initially vacuumed and wiped with masslinn cloths to remove any residual material that may have interfered with the alpha surveys (i.e., vacuum cleaning and usage of the masslinn cloth wipes removed dust and debris from the floors so that direct alpha measurements could be accurately obtained).

g During the performance of the final surveys no further decontamination was required (other than E

vacuuming and masslinn cloth wipes) in any areas of the building, south concrete footprint or the roof.

I Final Surveys Perforiued Obiectives and Resoonsibilities The objectives of the final survey plan were (1) to demonstrate that the average surface coatamination levels for each survey unit were below the approved release criteria, (2) to show that S ofl3

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• l> dMMIM AMEUCN Building 37 Final Radiological Survey Report the maximum residual activity 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 (i.e., vacuuming & masslinn wipes) and fixed contamination (if necessary) and (4) that the exposure rates in occupiable locations are less than 10 R/hr above background measured at I meter above the surface.

'I Surveys were taken only by qualified Health Physics Technicians having a minimum of three years Health Physics experience in accordance with approved Survey Plans. Samples were counted in GA's Health Physics Laborato:y which maintains an effective QA program.

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l Every survey conducted was documented on a daily basis to a worksheet/ drawing showing the approximate locations surveyed. The documentation included the results of the measurements (including units), the technician's signature, date, instmment(s) used (including the model and serial I

number of both the ratemeter and detector), calibration due date, % efficiency, background readings (if applicable) and any other pertinent information.

I Classification of Areas Non-Impacted Areas: The entire second floor and portions of the first floor (i.e., other than the High Bay Area and Rooms 110 and 112) have no history of radioactive material usage. Therefore, they were classified as "non-impacted" areas and require no radiological surveying. However, exposure rate measurements were conducted in these areas. These areas are shown in Figures 3 and 4.

Rooms 139 and 139A were classified as "non-impacted" and are located in the non-impacted area.

They were surveyed at an earlier date in order to remodel these areas. Consequently, in addition to I

conducting exposure rate measurements in these rooms they were scanned for alpha and beta 2

radiation with a 434 cm floor monitor and removable contamination surveys (wipes) were taken.

No contamination was detected in these two rooms. These rooms are shown in Figures 30 and 31.

The wall separating Rooms 139 and 139A was removed and a hole excavated through the concrete floor and into the soil beneath to accommodate future equipment foundations. The soil within the excavation was sampled and analyzed by gamma spectroscopy. Sample results were below or nur background levels. Figure 32 shows the location of the soil samples collected.

Unaffected Areas That portion of the High Bay Area used to temporarily store properly packaged I

low level radioactive waste from the SVA Decommissioning Project was classified as " unaffected" (see Figure 3).

In addition, rooms 110 and 112 where sealed sources were used, were classified as " unaffected"; no contamination was expected to be present. These rooms are shown in Figure 3.

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+).comurat arnames Building 37 Final Radiological Survey Report Since the SVA Decommissioning Project involved the decommissioning and dismantling of the northem halfof Building 37, the remaining southern portion of B 2ilding 37 adjacent to these activitics was subjected to an intensive survey investigation. Therefore, the northern portion of the I

high bay area was extensively surveyed to ensure that it was not contaminated during the decommissioning and dismantling operation (see Figure 3).

The south concrete footprint and the roof of the building were not expected to be contaminated and were classified as " unaffected areas." The south concrete footprint may be viewed in Figure 3 and the roofin Figure 29.

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Final Survey Plans g

Survey plans were developed based on the previous history of the building, the radionuclides of Ig concem, the various types of surfaces, the potential for contamination and the classification of the area (non-impacted or unaffected).

j The surveys included scanning of the floor and wall surfaces, collection and analyses (by gross alpha / beta counting) of smears, the taking of fixed measurements, exposure rate measurements

( R/hr), and sampling and gamma spec analyses of soil from rooms 139/139A and the roofing material (tar / insulation) from the roof.

The surveys were completed in accordance with approved written Final Survey Plans. Copies of the Survey Plans are provided in the Appendixes as follows:

Appendix A : Addendum to the " Final Survey Plan for Building-37 (SVA-South)" " Bldg. 37-(SVA-South)-Roof Sampling / Surveying Plan" dated July 31,1998.

Appendix B: " Final Survey Plan for Building-37 (SVA-South)" dated July 15,1998.

Appendix C: " Soil Sampling Plan for Building 37 - Rooms 139 and 139A" dated April 13,1998.

" Characterization and Final Survey Plan for Building 37 - Rooms 139 and 139A" I

dated March 12,1998.

I Samnle Preparation and Countine Each of the soil and roofing material samples collected were properly logged, labeled, packaged and tracked. Samples were dried, placed into a marinelli beaker, weigi'ed and counted by gamma spectroscopy. All samples were analyzed in GA's Health Physics Laboratory with a Canberra Low Sensitivity Gamma Spectroscopy MCA System using a high purity Germanium Detector. The system is calibrated using NIST traceable standards and performance checked daily.

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4==== mrmuses Building 37 Final Radiological SSEey Report Samples were counted for a minimum of 30 minutes each. A 30 minute count is sufficient to detect I

the radionuclides of concern at levels well below GA's approved release criteria.

Roofine Material Samples I

A Roof Sampling Plan was written to sample the tar and insulation from the roof of Building 37.

See Appendix A for the Sampling Plan.

I Soil Samnles Rooms 139 and 139A were surveyed at an earlier date in order to remodel these areas. The wall separating these two rooms was removed and a hole excavated through the concrete floor and into the soil beneath to accommodate future equipment foundations. The soil within the excavation was sampled and analyzed by gamma spectroscopy. See Appendix C for the Sampling Plan.

Survey Summary I

A summary of the number of fixed measurements, smears, exposure rate measurements ( R/hr), and samples taken during the Final Survey is provided below:

I Building 37 Final Survey Summary -

Survey

1. of Fixed

1. of Fixed

1. of

1. of Exposure Rate

1. of Samples Measurements Measurements Smears Measurements Taken and g

a

( R/hr)

Analyzed B

Roof Soil I

FinalSurvey 172 294 359 396 50 5

l Results of the Final Surveys The results for the Final Surveys are provided in Tables 5,6,7 and Figures 5 through 32.

Scanning 2

I Scans with the 434 cm alpha gas-flow proportional detectors (floor monitors) were conducted in the unaffected areas in order to identify elevated areas of activity. Areas with elevated readings would then be further investigated with hand-held a instruments / detectors to determine if the levels were above the release criteria. No areas were discovered that displayed elevated levels of a activity.

The results of these scans are provided in Table 5 and in the respective figures for each location.

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$ - ="AFOASCS Building 37 Final Radiological Survey Report 2

Scans with the 434 cm beta gas-flow proportional detectors (floor monitors) were also conducted in lg the unaffected areas in order to identify elevated areas of activity. Areas with elevated readings g

would then be further investigated with hand-held p instruments / detectors to determine if the levels j

were above the release criteria. The results of these scans are provided in Table 5 and in the

,E respective figures for each location.

Fixed Measurements A total of 172 fixed alpha measurements were performed during the final survey in the unaffected areas (i.e., floors, walls and south concrete footprint). The final measurements were taken using a 2

hand-held,50 cm gas-proportional alpha detector.

I One (1) minute fixed a measurements were taken. The applicable background for the 50 cm alpha 2

detector was subtracted fium the survey readings and these readings were converted from cpm to 2

dpm/100 cm using the appropriate count time, the efficiency of the detector and the geometry of the I

detector. The results are provided in Table 5 and the approximate locations are shown in their respective figures. All results were < 1000 dpm/100 cm,

2 A total o/1.94 fixed beta measurements were performed during the final survey in the unaffected areas (i.e., floors, walls and south concrete footprint). The final measurements were taken using a 2

100 cm gas-proportional beta detector.

One (1) minute fixed p measurements were taken. Tne applicable background for the 100 cm beta 2

I detector was subtracted from the survey readings and these readings were converted from cpm to 2

dpm/100 cm using the appropriate count time, the efficiency of the detector and the geometry of the detector. The results are provided in Table 5 and the approximate locations are shown in their 2

respective figures. All results were < 670 dpm/100 cm.,

Removable contamination surveys A total of 359 smears were taken during the final survey, Removable contamination measurements (smears) were performed on all unaffected area surfaces including the floors, walls, concrete footprint and overhead structures.

2 Smears consisted of using a Whatman Filter Paper (4.7 cm diameter) and wiping an area of ~ 100 I

cm. The smears were counted in GA's IIealth Physics Laboratory using a Canberra 2400 low level 2

2 alpha / beta counting system. The smear results in dpm/100 cm for both alpha and beta are pmvided in Table 5 and shown in their respective figures. The maximum smear results were 13 dpm/100 cm2 2

2 a and 17 dpm/100 cm p; well below the release criteria of 200 dpm/100 cm,

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• I*ammmm e er Building 37 Final Radiological Survey Report Masslinn surveys were also conducted on all floors by wiping the surfaces with masslinn cloths and I

measuring the activity on the masslinn cloths with a hand-held 15 cm GM pancake detector. All 2

readings were s to background measurements. The masslinn cloth wipes also removed dust and debris from the floors so that direct alpha measurements could be accurately obtained.

Exoosure Rate Measurements A total of 396 direct radiation exposure rate measurements were taken at various locations inside the tacility, on the roof and the outside concrete footprint. The measurements were taken at ~1 meter above the surface using a microR meter. The exposure rate measurements are provided in Table 5 I

and in the respective figures for each location.

1 I

Measurements inside the facility in the unaffected areas ranged from 10 to 16 R/hr. Measurements of the unaffected south concrete footprint outside the building ranged from 15 to 20 R/hr.

Measurements on the unafrected roof area ranged from 9 to 11 R/hr. Measurements inside the facility in the non-impacted areas ranged from 6 to 22 R/hr.

Roofine Material Samoles A total of 50 samples was collected from the roofin accordance with the Roof Sampling Plan. The locations are shown in Figure 29 and the results are provided in Table 6. The results of every sample showed levels were well below the release criteria.

Soil Samoles I

In Rooms 139 and 139A, a hole was excavated through the concrete floor and into the soil beneath to accommodate future equipment foundations. A total of 5 soil samples was collected from within the excavated area. Gamma spectroscopy results are provided for these samples in Table 7. The sample locations are shown in Figure 32. The results of every sample showed levels were well below the release criteria.

No further soil sampling was required in any of the areas in Building 37, since they were classified as either "non-impacted" W' unaffected, and no radioactive contamination was detected on any of I

the floor surfaces or walls.

g Conclusion Final contamination and radiation surveys, as well as soil and roofing material sample results, I

provided in this report for Building 37 demonstrate that the building, south concrete footprint and roof meet the approved guidelines for release to unrestricted use.

E 13 of13

!I I

1 I

\\

i Table li USNRC'S ACCEPTABLE SURFACE CONTAMINATION LEVELS 2 I

. Nuclides

Average */ -

Maximum 83 Removable *'

b b

b 2

2 2

-(dpm/100cm )

(dpm/100 cm )

- (dpm/100cm )

I U-nat, 235U,23:U, & associated decay 5,000 a 15,000 a 1,000 a products lB Transuranics,226Ra,228Ra, 23g, 22sTh, 100 300 20 g

23:pg 227Ac,123g,1291 Th-nat, 232Th, "Sr, 223Ra, 224Ra,232U,126I, 1,000 3,000 200 133g, i3ig 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 h,y as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency, an geometric factors associated with the instrumentation.

c Measureme.ats of average contaminant should not be averaged over more than 1 square meter.

For objects ofless surface area, the average should be derived for each such object.

2 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 I

by wiping that area with diy filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of I

known efficiency. W1 en removable contamination on objects ofless surface area is determined, then peninent levels should be reduced proportionally and the entire surface should be wiped.

f The average and maximum radiation levels associated with surface contamination resulting from 2

2 beta-gamma emitters should not exceed 0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm,

respectively, measured through not more than 7 milligrams per square centimeter of total absorber.

i T-1

! I

I Table 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS

. Nuclides".~

Average Maximum

• Removable * *'

~

W

(' dpm/100cm ) -

(dpm/100cm )

(dpnV100cm )-

2 2

2 U-nat,235U,238U, & associated decay 5,000 15,000 1,000 I

products Transuranics,226Ra,22 Ra, 23&I3, 22sTh, 100 300 20 23 Pa,227Ac, i253, i29; Th-nat, 232Th, "Sr, 22'Ra, 224Ra, 222U, 826I, 1,000 3,000 200

'2'I, *I I

Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 I

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.

Measurements of average contaminant should not be averaged over more than I square meter. For c

objects ofless surface area, the average should be derived for each such object.

d The maximum contamination level applies to an area of not more than 100 cm,2 2

e 'Ihe amount of removable radioactive material per 100 cm of surface area should be determined by 1

wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing I

the amount of radioactive material on the wipe with an appropriate instrument of known efficiency.

When removable contamination on objects ofless surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.

f The average and maximum radiation levels associated with surface contamination resulting from 2

2 beta-gamma c'nitters should not exceed 0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.

8 Guidelines For Decontamination of Facilities and Equipment Prior to Release for Umestricted Use or Termination of Licenses For byproduct, Source, or Special Nuclear Material, also known as "Decon-1" incorporated into GA's State of CA Radioactive Materials License.

T-2 I

I

. Table 3: List ofInstruments -

M ete.

Detector '

Detector Calibration -

Efficiency

= Range-

Background

Description S/N -

S/N Due Date --

(cpm)

(cpm).

r Ludlum Ludlum 120477 04-27-98 29.60 %

Four Linear See Table 4 he instrument is a gas-flow proportional counter Rate Meter Mode' 120477 10-20-98 31.68 %

Ranges with an active probe area of 100 cm,

2 Model 2221 4348 142540 11-03-98 26.76 %

0-500,000 S/N 86332 100 cm2 142540 01-14-99 28.80 %

& One Log Beta 142540 01-22-99 28.95 %

50-500,000 142540 03-02-99 29.80 %

142540 07-08-99 29.89 %

Ludlum Ludlum i19444 08-12-98 27.37%

Four Linear See Table 4 he instrument is a gas-flow proportional counter Rate Meter Model 119444 11-05-98 27.37%

Ranges with an active probe area of 100 cm.

2 Model 2221 43-68 03-11-99 27.25 %

0-500,000 S/N 84423 100 cm2

& One Log Beta 50-500,000 Ludlum Ludlum 083293 06-04-98 21.14 %

Four Linear See Table 4 He instrument is a gas-ilow proponional counter Rate Meter Model 094120 10-29-98 21.85 %

Ranges with an active probe are. of 434 cm. He detector 2

Model 2221 43-37 086213 01-07-99 22.04 %

0-500,000 and rate meter are combined and mounted to a roll S/N 84459 434 cm2 086213 07-14-99 21.27 %

& One Log around can. He instrument features a static-flow Beta 50-500,000 system, quick connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.

Ludlum Ludlum 086215 07-08-98 22.84 %

Four Linear See Table 4 He instrument is a gas-flow proportional counter l

Rate Meter Model 086215 01-06-99 22.84 %

Ranges with an active probe area of 434 cm. The detector 2

Model2221 43-37 086215 07-06-99 21.85 %

0-500,000 and rate meter are combined and mounted to a roll S/N 86302 434 cm2

& One Log around cart. He instrument features a static-flow Beta 50-300,000 system, quick connects, a portable gas bottle and a means to adjust the height of the detector from the i

floor for optimum paformance.

T-3 1

Table 3: List ofInstruments-Meter Detector.

Detector:.

CaBbration i

~ E!;kk-.;y e

.Rangej Backgror.nd.

Descriptum S/N-S/N.

~ Due Date

- (epm).-

- (cpm).

Ludlum Ludlum 086238 07-08-98 20.00 %

Four Linear See Table 4 The instrument is a gas-flow proportional counter Rate Meter Model 086238 08-27-98 20.00 %

Ranges with an active probe area of 434 cm. The detector 2

Model2221 43-37 086238 09-16-98 21.U %

0-500,000 and re.c, meter are combined and mounted to a roll S/N 97287 434 cm2 083265 11-19-98 21.69 %

& One Log amund cart. The instmment features a static-flow Alpha 083265 11-24-98 21.69 %

50-500,000 system, quick connects, a portable gas bottle and a 086238 11-27-98 21.90 %

means to adjust the height of the detector from the 086238 01-19-99 21.40 %

floor for optimum performance.

Ludlum Ludlum 086236 11-09-98 21.15 %

Four Linear See Table 4 The instrument is a gas-flow proportional counter Rate Meter Model 086236 04-20-99 21.65 %

Ranges with an active probe area of434 cm. The detector 2

Model2221 43-37 0-500,000 and rate meter are combined and mounted to a roll S/N 84734 434 cm2

& One Log around cast. 'the instrument features a static-flow Alpha 50-500,000 system, quick connects, a portable gas bottle and a means to adjust the height of the detector from the floor for optimum performance.

Ludlum tz:Eun 142349 04-27-98 21.58 %

Four Rzuges 0-5 Alpha scintillator ZnS(Ag) with an active probe area Model 12 Modet 142349 10-05-98 21.58 %

0-506,900 of 50 cm.

2 S/N 138738 43-65 142349 10-15-98 21.58 %

50 cm2 l

Alpha Ludlum Ludlum 145701 05-12-98 21.58%

Four Ranges 0-5 Alpha scintillator ZnS(Ag) with an active probe area Model 12 Model 145701 10-15-98 21.58 %

0-500,000 of 50 cm.

2 S/N 138747 43-65 145701 11-03-98 21.58 %

50cm2 145701 11-19-98 21.58 %

Alpha 145701 06-21-99 21.58 %

T-4 1

[

e e

e m

e e

e e

m e

m M

M M

M M

M M

Table 3: List ofInstruments-

' Meter

. Detector.

Detector -

Calibration.

- EilMency Range

Background

LW S/N S/N -

Due Date l (cysm)

' (cpm) -

Ludlum Ludlum 145696 04-15-98 21.58 %

Four Ranges 0-5 Alpha scintillator ZnS(Ag) with an active probe area Model 12 Model 145696 10-10-98 21.58%

0-500,000 of 50 cm.

2 S/N 138801 43-65 145696 10-15-98 21.58 %

50 cm2 145696 04-07-99 21.58 %

Alpha 145696 07-07-99 21.58 %

Ludlum Ludlum 145967 04-15-98 23.34 %

Four Ranges Concrete 80-120 His instrument is used for beta / gamma surveying.

Model3 44-9 145967 07-03-98 23.34 %

0-100,000 Concrete Block He detector has an active probe area of 15 cm.

2 S/N 143349 15 cm2 145967 10-21-98 23.24 %

60-140 Beta / Gamma 145967 g 02-19-99 22.24 %

Metal 80-120 Ludlum Ludlum 145963 04-15-98 23.24 %

Four Ranges Concrete 100-140 His instrument is used for beta / gamma surveying.

Model3 44-9 145963 10-08-98 22.05 %

0-100,000 Concrete Block He detector has an active probe area of 15 cm.

2 S/N 138880 15 cm2 145953 11-02-98 22.05 %

80-140 Beta / Gamma 145963 12-28-98 22.05 %

Metal 80-100 Ludlum RCA 6199 N/A 03-03-98 N/A Five Ranges 10-18 Used for measuring external dose rates on the surface Model 19 coupled to a 06-04-98 0-5 mR/hr pR/hr and at one (1) meter from the surface (i.e., initial Micro-R Na1(11) 06-05-98 l

gro md floor surveys). He scintillator [l"x 1" NaI Meter Scintillator 07-14-98 (11)]is mounted internally.

S/N 144022 10-06 98 Ludium RCA 6199 N/A 06-18-98 N/A Five Ranges 10-18 Used for measurmg extemal dose rates on the surface Model 19 coupled to a 0-5 mR/hr R/hr and at one (1) meter from the surface (i.e., initial Micro-R Nal(TI) ground floor surveys). He scintillator [1"x 1" Nat Meter Scintillator (TI)]is mounted internally.

S/N 87120 i

I T-5 i

e m

e e

e e

e e

ee e

e m

m mmm m

m Table 3: List ofInstruments Meter Detector -

Detector-Calibration Efficiency Range

Background

L' S/N S/N Due Date (cym) -

(cpm)

Ludlum RCA 6199 N/A 03-03-98 N/A Five Ranges 10-18 Used for measuring external dose rates on the surface Model 19 coupled to a 04-03-98 0-5 mR/hr pR/hr and at one (1) meter from the surface (i.e., initial Micro-R Nal(TI) 06-05-98 ground floor surveys). The scintillator [l"x 1" NaI Meter Scintillator 08-26-98 (TI)]is mounted intemally.

S/N 144068 11-03-98 Canberra Gas Flow N/A As needed

~ 26-36%

N/A Varies with Canberra Model 2400 Low Level alp gas proportional Low Level Proportional Sample counting system used to count wipes for removable alp Counter Counter contammation. Results are usually reported as 2

dpm/100 cm.

Canberra High Purity N/A As needed Varies with N/A Varies with Gamma Spectroscopy MCA system using a high Gamma Germanium Sample Sample purity Germamum detector. Used to identify U-235 Spectroscopy Detector (and other gamma emitters).

System T-6

l

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

Tcble 4: B:ckgreund Me surements(obt: Ired fr:m B:lidi:g 13)

Ludlum Model 2221 Rate Meter s/n 86332 with Model 43-68 probe s/n 142540 100 cm' Beta Detector (Efficiency = 28.80%)

Background Material Average of 10 Measurements at MDA q

1 minute ench (epm

• 20)

(dpm/100 cm')

I Concrete 531i56 381 Concrete Block 447 56 351 Metal 281

• 44 280 Drywall 287

• 44 283 I

Linoleum over Concrete 324

• 40 300 I

(Efficiency = 29.80%)

Carpet over Concrete 374 i35 311 Background Material Average of 10 Measurements at MDA I

2 minute each (cp2m

• 20)

(dpm/100 cm')

Concrete 1059

• 74 267 Concrete Block 919

• 108 249 Metal 550

• 52 194 Drywall 581

• 38 199 Linoleum over Concrete 686

• 44 216 Ludlum Model 2221 Rate Meter s/n 84423 with Model 42-68 probe s/n 119444 100 cm' Beta Detector (Efficiency = 35.50%) -

I Background Material Average of10 Measurements at MDA 2 minute each (cp2m

• 20)

(dpm/100 cm')

Concrete 1011

• 48 212 I

Ludlum Model 2221 Rate Meter s/n 86302 with Model 43-37 Probe s/n 086215 434 cm' Beta Floor Monitor Detector (Efficiency = 21.85%)

l Background Material Beta / Gamma Scan Range (cpm)

Concrete 1478-1765 Ludlum Model 2221 Rate Meter s/n 84459 with Model 43-37 Probe s/n 083293 8

434 cm Beta Floor Monitor Detector (Efficiency = 22.04%)

Background Material Beta / Gamma Scan Range (epm)

Concrete 1858-2036 Concrete Block 1174-1409 Drywall 770-937 Metal 816-1047 Carpet over Concrete 1030-1166 Linoleum over Concrete 1188-1462 T-7

l Table 4: B:ckgrsund Me:sureme:ts (obe:iEed fr:m driidiYg 13)

Ludlum Model 2221 Rate Meter s/n 97287 with Model 43-37 Probe s/n 086238 2

434 cm Alpha Floor Monitor Detector (Efficiency = 21.40%)

Background Mairrial Alpha Scan Range (cpm)

I Concrete 0-20 Conente Block 0-20 Drywall 0-15 Metal 0-20 I

Ludlum Model 2221 Rate Meter s/n 84734 with Nodel 43-37 Probe s/n 086236 2

434 cm Alpha Moor Monitor Detector (Efficiency 21.65%)

Background Material Alpha Scan Range (epm)

Concrete 4-24 Metal 2-20 I

I I

I I

I I

I T-8

m m

en m

e e

e ac m

m e

m Emu m

m m

m m

Tcble 5f Res lts cf Final Surveys intullding 37l(SVA-South):

Figure Location 2 # of Fixed a

Maxhnum a

. # of Fixed p Maxumun p Scan Results Scan Results

> # of

Mnin==> Result Exposure c

' Measurements Res :lt Measurements -

2 s

r

- Result 1

. 434 cm,

.434cm p 3,,,,,

(dpd100 cm y

_. Rate -

2 2

2

. 2 (50ctn detector)

(dpm/100 cm ).

(100cm detector).

(dpm/100 cm )

(cpm range)

(cpm range)

Range a

-Q (pR/br) ~

Unaffected Areas 5 thru North End 42

<MDA 97 611

<20 - 40 1200-1800 97

<10 14 10-15 9

Floor (121) 6 thru North End 11 139 11

<MDA

<20 700-900 11

<10

<10 9

Wall (<2m)

(194 metal)

(199 drywall) 10 Hallway 41

<MDA 34 604

<20 1300-1700 54 13 10 11-15 thru Floor (121) 13 14 liigh Bay 62 139 102 662

<20 - 20 1100-1900 46

<10 14 10-14 thru Floor 18 15 Iligh Bay 10 139 10

<MDA

<20 - 20 800-1300 10

<10 10 thru South Wall (381 concrete) 18

(<2m)

(280 metal) 19 High Bay 41

<10 10 Overhead 20 High Bay 27

<10 17 Overhead North West 21 Rooms thru 110/112 19 503 900-1100 20

<10

<10 12-16 24 Floor a

T-9 1

mm m

mm ee m

W W

W W

W m

W mW W

W Table 5: Results of Final Surveys in Building 37 (SVA-South);

Figure Location

1. of Fixed a Maximum a

1. ofFixed p ~-

Maxmmm p-Scan Results Scan Results

. # of f Maxmmm Result' Exposure Measurements

-Result '

Measurements Result -~

434 cm,-

434 cm p Smears 2

2

(

2

. dpm/100 cm ).

-- Rate 2

t 2

2

~

(50cm detector)

(dpm/100 cm )

(100cm detector).

(dpm/100 cm)

~(cpm range)

(cpm range)

Range (pR/hr) -

a-22 Rooms thru 110/112 13 340 800-900 16

<10 13 24 Walls (<2m) 25 South 6

<MDA 8

387

<20-60 2000-2300 16

<10 13 15-20 thru Footprint.

(121) 28 l

Masslinn (large area wipe) surveys were performed on Unaffected Area floors. Results: All wipess background p as read with 15cm GM detector.

2 29 Roof I

9-11 Results of 50 roofing material samples are found in Table 6.

Non-Impacted Areas 3

Ground Floor 11-18 4

Second Floor 6-17 30 &

Rooms 1-28 900-1880 8

<10

<10 31 139/139A Walls (<2m) 30 &

Rooms 1-32 1620-1980 13

<10 10 18-20 31 139/139A Floor 32 Rooms 20-22 139/139A Excavation T-10 i

I Table 6: Results of Roofing Material (tar and insulation) Samples Collected from Building 37 (Laboratory Count Times of 30 Minutes)

Radionuclide Concentration (pCi/g) '

Sample ID

... _ 22sTh Ra-Total Thorium 22:U 225U 22:

. Average of.

'(222 h) 1 I

583/238 kev -

Average of.

22 Th + 232Th-92.77 keVpeak 186 [144] kev peaks 338/911.. kev peaks peak' Bldg. 37 # 1 0.43 1.41 1.84 3.36 ND Bldg. 37 # 2 0.66 1.97 2.63 ND ND Bldg. 37 # 3 0.79 2.63 3.42 ND 0.32 Bldg. 37 # 4 0.67 1.74 2.41 1.99 0.28 Bldg. 37 # 5 0.70 2.20 2.90 ND ND Bldg. 37 # 6 0.77 1.86 2.63 ND ND Bldg. 37 # 7 0.42 2.37 2.79 5.62 0.32 Bldg. 37 # 8

• 0.53 1.20 1.73 2.56 0.19 Bldg. 37 # 9 0.76 1.78 2.54 3.58 ND I

Bldg. 37 # 10 0.60 1.61 2.21 3.59 ND I

e e

Bldg. 37 # 12 0.82 2.85 3.67 4.25 0.40 Bldg. 37 # 13 0.50 1.49 1.99 ND ND Bldg. 37 # 14 0.66 1.50 2.16 ND 0.31 Bldg. 37 # 15 0.31 1.26 1.57 ND ND I

Bldg. 37 # 17 0.64 1.89 2.53 3.54 ND Bldg. 37 # 18 0.90 1.97 2.87 ND ND lI Bldg. 37 # 19 0.53 2.57 3.10 5.97 0.57 i

T-ll I

I

I

Table 6: Results of Rooring Material (tar and insulation) Samples Collected from Building 37 -

Raboratory Count Tl= of 30 MinutesF Radionuclide Concentration (pCi/g) '

SampleID 22sTh 228Ra-

. Total Thorium

"'U'-

2"U Average of.

- (u2Th)

I 583/238 kev'

- Average of 22eTh + 232Th 92.77 keVpeak 186 [144] kev peaks 338/911 kev peaks peak' Bldg. 37 # 20 0.46 1.14 1.60 ND ND Bldg. 37 # 21 0.97 2.18 3.15 3.66 0.51 Bldg. 37 # 22 0.48 1.50 1.98 4.03 ND Bldg. 37 # 23 0.75 2.21 2.96 3.08 0.50 Bldg. 37 # 24 0.61 ND 0.61 1.79 ND Bldg. 37 # 25 0.43 1.88 2.31 2.14 0.31 Bldg. 37 # 26 0.70 1.61 2.31 4.36 0.35 Bldg. 37 # 27 0.65 1.80 2.45 3.08 ND Bldg. 37 # 28 0.58 2.64 3.22 3.84 0.39

,I Bldg. 37 # 29 0.60 2.19 2.79 3.16 ND Bldg. 37 # 30 0.46 1.92 2.38 4.05 ND Bldg. 37 # 31 0.63 1.99 2.62 4.29 ND Bldg. 37 # 32 0.74 3.08 3.82 7.31 0.52 Bldg. 37 # 33 0.85 1.42 2.27 4.33 0.41 Bldg. 37 # 34 0.77 1.84 2.61 ND ND Bldg. 37 # 35 0.73 1.50 2.23 4.53 0.29 Bldg. 37 # 36

• 1.89 5.05 6.94 1.42 0.37 Bldg. 37 # 37 0.61 2.19 2.80 4.00 0.29 Bldg. 37 # 38 0.67 1.77 2.44 2.30 0.29 T-12 I

E

I lI I

Table 6: Results of Roofing Material (tar and insulation) Samples Collected from l

Building 37 l

(Laboratory Count Times of 30 Minutes) l Radionuclide Concentration (pCVg) '

i l

SampleID Th 22: Ra-Total Thorium 23sU 2"U 22 l

. Average of '

_ (232Th) 583/238 kev Average of.

22sTh + 2321h 92.77 keVpeak 186 [144] kev j

peaks 338/911 kev peaks peak Bldg. 37 # 39 0.72 1.53 2.25 5.32 0.47 l

Bldg. 37 # 40 0.44 1.92 2.36 ND 0.20 Bldg. 37 # 41 0.68 1.73 2.41 2.43 0.46 Bldg. 37 # 42 1.92 6.75 8.67 ND ND E

Bldg. 37 # 43

• 0.74 1.48 2.22 2.57

[0.50]

Bldg. 37 # 44 0.60 3.66 4.26 5.52 0.69 Bldg. 37 # 45 0.70 1.33 2.03 2.07 0.24 Bldg. 37 # 46 0.77 2.00 2.77 4.10 0.46 l

Bldg. 37 # 47 0.52 1.44 1.96 3.90 ND I

Bldg. 37 # 48 0.78 1.29 2.07 2.97 0.29 Bldg. 37 # 49 0.48 1.54 2.02 2.11 0.37 Bldg. 37 # 50 0.53 1.55 2.08 2.77 0.36 3 Background concentrations not subtracted from the results.

• 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> laboratory count times.

I E

I l

1 T-13 I

lI

I Table 7: Results of Soll Sample Results Collected in Rooms 139 and 139A (Laboratory Count Times or30 Minutes) -

Radionuclide Concentration (pCi/g) '

22 Sample ID Th 22 Ra Total'Ihorimn 25'U 235U Average of (232Th) 583/238 kev Average of 22 Th + 232Th 92.77 keVpeak 186(144) kev peaks 338/911 kev peaks peak Bldg. 37 # 1 1.00 1.66 2.66 1.91 0.15 Bldg. 37 # 2 0.85 1.36 2.21 2.21 0.13 Bldg. 37 # 3 0.27 0.43 0.70 0.70 0.07 I

Bldg. 37 # 4 0.72 1.14 1.86 1.58 0.15 Bldg. 37 # 5 0.32 0.85 1.17 1.42 ND

' Background concentrations ncl subtracted from the results.

I I

I I

I E

I E

iI i

T-14

'I

l I

Table 8: Background Soll Sample Results 8 g

Radionuclide Concentrations (pCi/g) _

Sample Th-228 Ra-228 Total Thorium U-238 U-235 I

ID 2 Average of (Th-232) 238/583 kev peaks Average of 338/911 Th-228 + Th-232 92.77 key eak I86 (144) kev p

kev peaks peak AJ 1.28

• 0.07 1.47

• 0.14 2.75 1.98

• 0.31 0.15

• 0.03 G2 0.92 0.07 1.01 0.12 1.93 1.86 0.29 0.12

• 0.02 AC 1.29

• 0.07 1.3410.14 2.63 2.27

• 0.27 0.20 t 0.03 BKG-1 1.40

• 0.16 1.44

• 0.28 2.84 2.06 0.48 0.19 i 0.06 BKG-2 1.54

• 0.15 1.57

• 0.27 3.11 2.30

• 0.45 0.17

• 0.05 BKG-3 1.40

• 0.14 1.62

• 0.26 3.02 ND 0.19 i 0.05 BKG-4 0.67

• 0.00 0.84 0.17 1.51 1.15 i 0.37 0.09 0.04 BKG-5 1.51

• 0.16 1.79 0.31 3.30 2.77

• 0.67 0.12

• 0.06 BKG-6 0.68 0.09 0.76

• 0.16 1.44 ND 0.08

• 0.03 BKG-7 1.17

• 0.12 1.28

• 0.22 2.45 1.83

• 0.43 0.11

• 0.04 Mean

• 2 a 1.19 i 0.64 1.31 i 0.68 2.5 i 1.32 2.03 i 0.93 0.14 i 0.09 Samples gamma scanned for I hour.

ND = < l.0 pCi/g for U-238 2

Samples collected in June and August 1993, typically about ! 'l miles from the Building 37 site at the following locations:

AJ Collected on a hillside west of Building 39 & northwest of building 37, ~3' from GA's fence.

G2 Collected about 1200 feet west of Bldg 1 (near T.P. RD.), and ~7/8 of a mile southwest of I

Building 37.

AC Collected about 1 mile southeast of the main site & about 2 miles southeast of Building 37.

I BKG-1 Collected about I mile from Building 37 at the Senpps Hospital Entrance, east of Genesee Ave.

BKG-2 Collected about 1.2 miles from Building 37 at Sorrento Court Rd. by North entrance to Post Office.

BKG-3 Collected about 1.5 miles from Building 37 at Sorrento Vista Parkway near Lusk Blvd. South.

BKG-4 Collected about I mile west from Building 37, west off Genesee corner of North Torrey Pmes Road and Torrey Pines Scenic Dnve BKG-5 Collected about 2 miles west of GA off of La Jolla Shores Drive.

BKG-6 Collected about 2 miles northwest of Building 37 on North Torrey Pines Road BKG-7 Collected about 2 miles near V.A. Hospital on La Jolla Village Drive (southwest) lu T-15

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1.

Survey resu!ts are provided in Table 5.

2.

All concrete surfaces.

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M Figure 14: High Bay Area: Locations of Large Area Masslinn Wipes E

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2.

No activity above background was found.

3.

A!! concrete surfaces.

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2.

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3.

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4.

Exposure rate measurement (s) ranged from 10pR/hrto 14 IWr.

5.

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No activity above background was found.

Figure 22: Rooms 110 & 112: Beta Scans on Walls and Floors OL A

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1.

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4

g 2.

-10% of the floor and walls were scanned for p.

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3.

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Figure 23: Rooms 110 &112: Locations of Fixed Beta Measurements lE on the Walls and Floors and Exposure Rate Measurements 9t

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Notes:

1.

Survey results are provided in Table 5.

2.

The Squares are the approximate locations of measurements taken. One minute (cpm) fixed p readings were taken.

3.

Exposure rate measurement (s) ranged from 12pR/hr to 16 R/hr.

^ " " " " " ' " " * ' " " " " * " " " ' " " ' ' " " " " " ' '

!I

I Figure 24: Rooms 110 & 112: Removable Contamination Locations on the Walls and Floors I

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Note:

I The numbers circled are approximate locations of wipes taken. Shaded numbers circled denotes wall wipes.

Survey results are provided in Table 5.

.I

!I

I I

Figure 25: South Concrete Footprint: Location of Large Area Masslinn Wipe I

A h

Room 139 Room 139 A Non-Impacted Area E

C i

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High Bay Area l

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" Foot Print" I

UnaffectedArea a

3 I

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~ Non-Impacted Area c[ 7

... O.!...O O

O.

.. C.

Non-Impacted Area I

Note:

1.

Approximate location of large area masslinn wipe taken on the South concrete Foot Print.

2.

No activity above background was detected.

3.

All concrete surfaces.

I A

. ~. - -. -

lI I

Figure 26: South Concrete Footprint: a and p Scan and Exposure Rate Measurements.

I TD h

Y Room 139 Room 139 A I

C Non-ImpactedArea I

a

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Non-Impacted Area

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0.

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Notes:

1.

Survey results are provided in Table 5.

2.

~25% of the concrete pad was scanned for a and p.

i 3.

Exposure Rate Measurements were taken and results ranged from 15 R/hr to 20 R/hr.

4.

All concrete surfaces.

I

1 Figure 27: South Concrete Footprint. Locations of Fixed a and E Fixed Measurement s l

TD l

A

,wwh y

G Room 139 Room 139 A Non-ImhactedArea I

C

^

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d.

High Bay Area i

t South Concrete Pad

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W 8

.U

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l c

8 Room 112 Y

l Non-Impacted Area q

,.. 0 ;

.. O..._.. O O...

t

@c-Non-impacted Area Notes:

1.

The Squares are the approximate locations of measurements taken.

Survey results are provided in Table 5.

2.

All concrete surfaces.

I I

Figure 28: South Concrete Footprint: Removable Contamination Locations

'S

&4

> tR

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E Room 139 Room 139 A Non-Impacted Area I

C I

m.

m n

High Bay Area E

South Covcrete Pad

• Foot Pn'nt"

I UnaffectedArea

• ~

I 9

d g

w 9

c

@^

Room 112 O

I

~~ Non-Impacted Area R'

R

.0 D.

C I

g

.g g

Non-Impacted Area Notes:

The numbers circled are approximate locations of wipes taken. Wipe results are provided in Table 5.

1.

2.

All concrete surfaces.

I I

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m Figure 30: Rooms 15 ' and 139A: large Area Masslinn Wipes and Removable Contamination Locations and Exposure Rate Measurements y

54

• s V

E f

WALL E'

19 pR/hr 20 pR/hr 20 R/hr 19 pR/hr 20 p%r I' "

rg rr j

@p

^

WAu WALL 20 pR/hr FLOOR 20 pR/hr 20 pR/hr w

Room 139

,t Room 139a 20pR/hr

l b

l 19 pR/hr 20pR/hr 20 pR/hr WALL WAu b

NOTES:

1.

Survey results are provided in Table 5.

2.

The numbers circled are the approximtie locations of wipes taken.

3.

Exposure Rate Measurements were taken at 1m above the ground. Results ranged from 18 to 20 pR/hr.

4.

The lettered squares are the approximate locations of large area wipes taken. No activity above background was detected

Figure 31: Rooms 139 & 139A: Alpha / Beta Scans on Walls and Floor

=

34

> *JL Y

.1 to 28 cpm a waB scan WALL s

Q ;'

x

[

900 to 1880 cpm p wau scan

,3 s

s s

s X.

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s N

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_N

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- sy s

s WALL

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=

!A 1.

Survey results are provided in Table 5.

2.

~100% of the floor was scanned (in cross hatched area) for a and.

3.

~25% of the wall was scanned (in cross hatched area) for a and p.

4.

All drywall and metal walls and concrete floor surfaces.

w w

Figure 32: Rooms 139 and 139A (Excavation): Soil Sample Locations and Exposure Rate Measurements 4

3 M

.u 6

WALL l%Nh ll

?i Y y~ J gy y 3;

k3edtar1 Mll i

gy ip-s4?%!!1??y %

j

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V A Y$I FLOOR E 4p - Excevetiony%

J NNill L51.b~

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-%.jiN '

s

-;f

+ g.-w; 11JIsakr-KA h wh--s 'Trs j, w;

?MMist@

=-

H WALL' WALL

\\

s NOTES:

)

1.

The numbered squares are the approximate locations of dirt samples taken.

2.

Soil results are provided in Table 7.

3.

Exposure Rate Measurements were taken in the excavated area -1m from bottom of the pit. Resu% ranged from 20 to 22 pR/hr.

4.

All dirt surfaces.

I Appendix A to I

Final Radiological Survey Performed at General Atomics' Building 37 Non-impacted and Unaffected Areas dated g

January 29,1999 I

I I

I S

Addendum to the " Final Survey Plan for the Building g

37 (SVA-South)"

" Bldg. 37-(SVA-South)-Roof Sampling / Surveying Plan" I

dated July 31,1998 I

I I

I t

~ -. - -.... -.. -

!I

[GENERALATOMICS

!e INTERNAL CORRESPONDENCE 1l l

[

In Reply From:

Laura GonzaMs/ John Tumer Refer To:

LQG:98:131 E

To:

Distribution Date:

July 31,199 I

An addendum to the " Final Survey Plan for the Building 37-(SVA-South)" was generated by J.

Turner to address the sampling / surveying of the building's roof.

E ;)

Please call John Tumer at X2068 if you have further questions regarding this matter.

I h

cc:

w/o attachments K. Asmussen B. Noren 8

F. Dahms w/ attachments I

P. Maschka C. Stanley B. Lyons E

I I

July 31,1998 g

MPaul Maschka/ John Tumer re: LQG:98:125, " Final Survey Plan for the Building-37 (SVA-South)"

Appmved by: Laura Gonzales Q1u o_ M mhh 1 V 3 U

~

Addendum to the " Final Survey Plan for the Building 37-(SVA-South)"

g Bldg. 37-(SVA-South)-Roof Sampling / Surveying Plan Purpose The purpose of this sampling / survey plan is to ensure that residual contamination in the roofm' g materials (i.e., tar / tar paper and insulation) is below the approved release criteria specified in GA's Site Decommissioning Plan.

I Classification The roof of Building 37 (SVA-South) is classified as " unaffected". If contamination a 75% of guideline limits is encountered, the roof will be reclassified.

y Guideline levels

-}

The release criteria for roofing material (i.e., tar / tar paper and insulation) is specified in the Site Decommissioning Plan and summarized below for the radionuclides ofinterest at Bldg. 37.

Cs-137 15 pCi/g Co-60 8 pCi/g i

Enriched Uranium (U-234 plus U-235) 30 pCi/g Thorium (Th-232 plus Th-228) 10 pCi/g Natural Uranium (U-238) 35 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.

The guideline value for exposure rates measured at 1 meter above the surface is 10 microR/hr above background. Background is typically - 15 microR/hr, but may vary with type of facility and location. The Alert Level is 20 microR/hr.

Sampline Procedure I

1.

Samples will be obtained at an interval of approximately I every 7 meters. The samples will be obtained at a distance of a 6 feet from the edge of the roof (for safety purposes).

2.

Obtain individual samples of the roofing material (i.e., tar / tar paper and insulation).

~~

Permission was obtained from Leticia Alfonso to obtain these samples even if they

)

)

e,

contain asbestos. L. Alfonso will be given a non-contaminated sample for asbestos

)

analysis.

3.

Insulation samples will be taken separately from the taritar paper samples only if the insulation is > ~ 1" thick. Sample and package each of the layers separately (i.e., tar / tar paper to 100 ml containers and insulation,if taken, to 100 ml containers). Flag or mark each sample location on the roof for future reference.

4.

Place each individual sample into their appropriate containers and transpon the samples to the HP Counting Laboratory, log the samples and have all the samples gamma scanned.

Samples are not expected to contain radioactivity > background levels and themfore can be transponed to the main site per 49CFR173 (<0.002 nCi/g is not considered radioactive per DOT).

Survey Procedure I

Take microR measurements at approximately I every 3 meters. Take microR measurements, at each applicable location, on the surface of the roof and at I meter from the surface of the mof.

Documentation Document the sampling locations on a building drawing showing the appropriate locations sampled. The documentation must include the technician's printed name and signature, date and

')

any other peninent information.

Document the microR measurements and locations to a building drawing. The documentation I

must include the results of the measurements (including units), the technician's printed name and signature, date, instrument used (including the model number and serial number of the detector),

I calibration due date, % efficiency, background readings (if applicable) and any other peninent information.

t I

I l

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I ll Appendix B to i

Final Radiological Survey Performed at General Atomics' I

Building 37 Non-impacted and Unaffected Areas dated

!I January 29,1999 ll

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g

" Final Survey Plan for the Building-37 (SVA-South)"

I dated July 15,1998 I

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T s

kdomanumJeromets INTERNALCORRESPONDENCE L. Gonzala&

d From:

r/J. Tumer In Reply Refer To:

LQG:98:125 To:

Distribution Date:

July 15,1998

Subject:

Issuance of the Final Survey Plan for the Building-37 (SVA. South)

The Final Survey Plan for Building 37 (SVA-South) has been completed. The Plan was reviewed and discussed with the following HP Technicians: Comelius Stanley and Barbara Lyons.

i cc:

w/o attachments I

K. Asmussen F. Dahms with attachments P. Maschka C. Stanley B. Lyons B. LaBonte l

D. Keesling

---

q 1

[

July 14,1998 Page 1 of 5 Date: July 14,1998 p2#

Prepared by: John Turne i

Approved:

Laura Gonzales Mni un. b %AoM Date Cab N,l %~

U 0

0 Survey Plan for the Building-37 (SVA-South) 2 rurnose The purpose of this survey is to ensure that residual contamination in the building is below the approved release criteria specified in GA's Site Decommissioning Plan by performing this Final Survey. The roof will be addressed in a separate plan.

Backeround The remaining portion of Building 37 is currently being used for non-radioactive work. It had previously been used for storage of properly packaged radioactive waste from the SVA Decommissioning Project.

Scaled sources were also used by the Triga Reactor Division in Rooms 110 and 112 for the calibration of nuclear instrumentation. No sesidual radioactivity is expected to be encountered in this facility.

Classification of Various Areas of the Buildine (see Firures I and 2)

."Non-impacted Areas"- The entire second floor and portions of the first floor have no history of radioactive usage. Therefore, they are classified as "non-impacted" areas and require no radiological

. }

surveying. Howeve:, exposure rate measurements (micro R scans) will be conducted. Refer to figures 1 and 2 for the location of these areas.

"Unaf7ected Areas" - Although a porti<m cf N High Bay area (noted in Figure 1) was used in the past to store radioactive mate ia! Tmm the SVA Decommissioning Project, only properly packaged waste was stored here after surveys wep, conducted to demonstrate that contamination levels on the outside of the containers were below the release criteria. In addition, only sealed radioactive sources were used in rooms 110 and 112 for calibration of TRIGA monitoring / control equipment. Therefore, the area is classified as "enaffected"; no contamination is expected to be present.

The only outside area to be surveyed will be the building's ingress / egress (footprint) to the south of the High Bay Area (approximately 90 m'of concrete surface). Tia north side area footprint was addressed during the SVA-North Decommissioning Project. The sidewalk and landscaping in this area were constructed after the SVA-North decommissioning / release. The eastern and western exterior footprints of the building will be dealt with when the surrounding "open" land areas are addressed.

Unaffected AreaClassification The following depicts the division of the first floor " unaffected" areas into three (3) distinct portions that l

reflect their past history of radioactive material usage.

I

' The north portion of Building 37 (called the "SVA Fuel Manufacturing Facility") was decommissioned between 1990-1995. After NRC and State of CA approval, the building was dismantled and the site subsequently released to unrestricted use. This Survey Plan is for the remaining portion of the l-

)

building which was not released to unrestricted use at that time.

lh-ig]

July 14,1998 Page 2 of 5 (A)

Rooms 110 and 112 contained beta / gamma sealed sources such as Cs-137.

(B)

Rooms 127A,128,129, and 130 of the High Bay area served as storage areas of properly packaged radioactive waste. Rooms 127S2,127S3,125S3,126S3,126A and 125A will also be surveyed.

(C)

Footprint to the south ingress / egress of the HIGH Bay Area (concrete creas only).

Description

" Unaffected Areas" m

2 (A) Rooms 110 & 112 126 (B)High Bay Area 1,045 (C) South Footprint 90 I

Total 1261 m2 l

1 Release Limits 0* r GA Site Decommissionine Plan) i I

Facility Structure Criter_ia The primary contaminants of concern for this site are natural thorium and enriched uranium. The applicable guidelines for residual contamination on building surfae's for enriched uranium are:

Enriched Uranium

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.. 00 dpm or/100cm2, total, averaged over a 1 m area 2

15,000 dyn; O.0cm2, total, maximum in a 100 cm area 2

1000 dpm or/w0cm2, removable activity In Building 37, the alpha surveys are sufficient to determine compliance with the release criteria, although some beta monitoring will also be performed (for thorium). Alpha measurements are satisfactory for the following reasons:

l.

In " highly" enriched uranium (uranium used in the facility was typically - 93% enriched); alpha monitormg is the method of choice. At this enrichment, the U-234 activity present has incarased signifimady. The alpha to beta ratio is approximately 116:1.2Because of this, alpha mortitoring is l

the measurement of choice for enriched uranium.

2.

Alpha surveys are accurate if the surface is clean, free of paint or other coverings and free of dust and debris. All surfaces will be clean before scanning or fixed measurements are performed.

I 3.

It is GA's goal to decontaminate the building structure to levels < 1000 dpm cr/100cm (thorium 2

tirnit).

l 2

)_

From Table 5-4 of ' ilealth Physics Manual of Good Practices for Uranium Facilities" Prepared for DOE by Idaho National Engineering Laboratory, document EGG.2530, UC-41, dated June 1988.

l

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July 14,1998 Page 3 of a

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Aloha Alert Values If the following " alert levels" are exceeded, notify HP Management so an evaluadon can be performed to i

determine ifincreased survey coverage is required or to evaluate if decontamination is required.

> 150 cpm alpha using the large area (434 cm ) probe 2

> 75 cpm using a hand-held alpha probe (~ 750 dpm/100cm )

2 Natural Thorium I

2 1000 dpm/100cm2, averaged over a 1 m area

/

2 3000 dpm/100cm2, maximum in a 100 cm area 200 dpm/100cm2, removable activity I

As interpreted by the NRC, the average 1000 dpm/100cm2 and the maximum 3000 dpm/100cm should 2

apply to both alpha and beta measurements, independently, for surface contamination involving natural thorium.8 Alpha measurements will be performed to detect < 1000 dpm cx/100 cm,

2

'Ihorium emits alpha radiation to beta radiation in a 1:0.67 ratio; therefore, the corresponding average and I

maximum beta activity guidelines were adjusted to be 670 dpm/100cm2 and 2000 dpm/100cm2, respectively, for beta monitoring.

Beta Monitoring - Each fixed measurement will be reviewed and evaluated.

Beta Guideline Values (thorium)

I

)'

2 2

670 dpm/100 cm averaged over a 1 m area 2

2 2000 dpm/100 cm maximum in a 100 cm area 2

200 dpm ot/100 cm removable activity A 1 minute fixed measurement using the 100 cm gas flow detector, gives an MDA < 500 dpm/100 cm.

2 2

One minute beta fixed measurements will also be performed to demonstrate that the thorium limits have been met.

Beta Alert Levels

> 300 cpm beta above background using the large area (434 cm ) probe 2

2

> 150 cpm above background using the 100 cm probe Exposure Rate Level The guideline value for exposure rates measured at I m above the surface is 10 microR/hr above a

background.

I Exposure Rate Alert Background is typically - 15 microR/hr (but can vary with type of facility and location). Alert Level is 20 pR/hr.

I

' " Interpretation of Thorium Surface Decontamination Limits," U.S. Nuclear Regulatory I

Commission, Febmary 9,1992.

I I

July 14,1998 Page 4 of 5 Soil Sampline Some soil samples have been collected from undemeath the building slab. The need for additional samples will be evaluated by Health Physics and if determined to be needed, a Soil Sampling Plan will be issued.

Soil Release Criteria Enriched Uranium (U-234+U-235) 30 pCi/g Thorium (Th-232+Th-228) 10 pCi/g For 93% enriched uranium, the U-234:U-235 ratio is about 30:1; therefore, ~1 pCi/g of U-235 means 30 pCi/g total U-235+U-234. Alert level is set at 0.7 pCi/g U-235.

Documentation Every mdiological survey conducted must be documented on a daily basis to a worksheet/ log book and on a drawing showing the appropriate locations surveyed. The documentation must include the results of the measurements (including units), the technician's printed name and signature, date, instrument (s) used (including the model and serial number of both the ratemeterand the detector), calibration due date, %

efficiency, background readings (if applicable) and any other pertinent information.

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E, lI' July 14,1998 Page 5 of 5 Planned Surveys for Unaffected Areas of Building 37 i

Area A Area B Area C Type of Survey (IVysources only)

(High Bey Area)

(outside area - south end) l Masslin Surveys Yes Yes Yes Concrete Floor

• 10 %

25% a,25%

• 25% a,25%

l (Sc*a */434 c"'P'**)

1005 Cross Hatched Area (See Figure 1)

Lower Walls Scan 10 %

10 % a,10 % p Not Required

'I (bottom 2m)

(only the north and south (scan w/ 434 cro 'pmbe) unaffected walls to be done; not i

non-impacted area walls) l I' Walls Scan Not Required Not Required Not Required (above 2 m)

' 3'~

Number of Planned Measurement every ~4 m Measurement every ~4 m Measurement every ~4 m ig Measurements" "'

Alternate between (I) a Alternate between (1) a removable Altemate between (1) a removable removable and (2) a beta fixed (2) a beta fixed measurement and (2) a beta fixed measurement and measurement on the floor and (3) an alpha fixed measurement, on (3) an alpha fixed measurement, on walls the floor and walls the concrete

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pR/hr Readings 1 every 3 m i every 3 m I every 3 m

@ Im from surface N_ote: Take MicroR surveys in "non-imacted" areas also: Take I measurement / room (at im above the surface)

Floor Surface Tile and Carpet Concrete Concrete Roof A separate plan will address the roof of Building 37 2

Smears Take ~ fifty (50)- smears 10') cm on horizontal overhead surfaces; evenly distributed in unaffected areas.

ll Clean all surfaces to remove debris or dirt (wash, mop and/or vacuum, as needed).

l5 If contamination above background is detected on any of the floor surfaces. Health Physics will evaluate the

)

need for additional survey coverage. Survey coverage will be instituted if contamination levels above 75%

are detected (the Site Plan requires re-classification if levels >75% are detected).

For the fixed measurements:

For a measurements; use the hand held alpha counter (~5-10 second count). Document all e

I readings in epm.

l -f 7.,2 3 - TI For measurements; take a/ minute count using the I cm gas flow proportional detector 2

(beta) with the Model 2221 ratemeter. Take additional

• ugtgnggurements in selected decontaminated areas of walls and other areas. Documen readmgs an3 mark on a drawing I

where the readings were taken.

Take fixed measurements on wall -1 meter from floor surface.

(4) 2 For removable measurements, take a 100 cm wipe at each location; count using a low level a/ counter.

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s Figure 1 Yellow - Non-Impacted Area Blue - Unaffected Area Blue-Cross Fr ched - 100% Coverage r

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I Appendix C I

to I

Final Radiological Survey Performed at General Atomics' Building 37 Non-impacted and Unaffected Areas dated I

January 29,1999 I

I I

l

" Soil Sampling Plan for Building 37 - Roen:s 139 and 139A" g

dated April 13,1998 i

i

" Characterization and Final Survey Plan for Building g

37 - Rooms 139 and 139A" I

dated March 12,1998 I

i I

1

i I

1 Date: April 13,1998 Paul Maschka l

SOIL SAMPLING PLAN FOR BUILDING 37-ROOMS 139 AND 139A 1.

Obtain a to'al of 5 individual soil samples at a depth of 0-6" (15 cm) from within the excavated " pit". Obtain a volume of soil that will completely fill a marinelli beaker.

2.

Take microR readings at I meter from the bottom surface of the pit at each sampling location.

4.

Dry the 5 samples and place each sample into individual marinelli beakers. Transport the samples ta tia HP Counting Laboratory, log the samples and have all 5 samples gamma scanned for 30 m'nutes.

i i

5.

Document the surveys and soil sampling locations to the survey worksheet and attach the drawing showing the appropriate locations surveyed / sampled. The documentation must

)

include the results of the measurements (including units), the tc.chnician's printed name i

and signature, date, instrument (s) used (including the model and serial number of both the ratemeter and the detector, if applicable), calibration due date, % efficiency, backgrcund g

readings (if applicable) and any other pertinent information.

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' I 'd Date: March 12,1998 PaulMaschka / Aft /

l Characterization and Final Survey Plan for Buildug 37-Rooms 139 and 139A Building 37 contains two rooms (139 and 139A) which need to be surveyed in order to be remodeled. The two rooms are located in a "non-impacted area" but will be surveyed before remodeling to ensure that these rooms are not radiologically contaminated in any manner.

1.

Conduct masslinn surveys of the floor and check the cloths for alpha and beta contamination.

@5 2.

Scan 100% of the surface of the concrete floor for both alpha and beta with the 434 cm2 floor monitor.

I 3.

Scan 25% of the walls up to two meters for both alpha and beta with the 434 cm probe.

2 4

4.

Take 10 wipes per room.

5.

Take general microR scans and readings every 3 meters on contact and at one meter l

above the surface.

i 6.

Document the surveys and locations to a survey worksheet and attach the drawing showing the appropriate locations surveyed. The documentation must include the results of the measurements (including units), the technician's printed name and signature, date, instrument (s) used (including the model and serial number of both the ratemeter and the

'I detector, if applicable), calibration due date, % efficiency, background readings (if applicable) and any other pertinent information.

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