ML20198P257

Final Radiological Surveys of Selected Portions of Bldg 39 (Svb) to Be Released to Unrestricted Use

ML20198P257
Person / Time
Site:	07000734
Issue date:	12/09/1998
From:	Cowan S, Maschka P, Sullivan J GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
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NUDOCS 9901070017
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CEN2HL ATOMICS i

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FINAL RADIOLOGICAL SURVEYS OF I

SELECTED PORTIONS i

i OF BUILDING 39 (SVB) TO BE RELEASED TO UNRESTRICTED USE i

l Prepared By: Paul Maschka, Joe Sullivan, Scott Cowan and Laura Gonzales, Date: December 9,1998 9901070017 981222 Us PDR ADOCK 07000734 C

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$W FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 TABLE OF CONTENTS i

EAAC Li s t o f Tables.....................................

.........I i

Lis t of Figures..........................

......................i Introduction................

1 S it e Descrip tl n..................................

1 Previous Activities (History of Use).....

2 Criteria for Release to Unrestricted Use..............

2 Instrumentation.........

4 Background Measurements 4

Decontamination Activities 5

Final Survey Plans 6

' Results of Final Surveys............

8 Conclusion....

11 LIST OF TABLES Ea2C Table 1:

USNRC's Acceptable Surface Contamination Levels..

12 Table 2:

No Table 2 Table 3:

List of Instruments 13 Table 4:

Background Measurements and MDA's 16 Table 5:

Results of Final Surveys in Building 39 18 Table 6:

Paint Sample Results.....

21 Table 7:

Soil Sample Results from Underneath Office Area Floor 23 Table 8:

Roof Gravel Sample Results....................................

24 Table 9:

Background Soil Sample Results 28 t

Table 10:

Background Gravel Sample Results 29 LIST OF FIGURES (unn. aced)

L Figure 1:

Plan View of General Atomics Site Figure 2:

Sorrento Valley Site Figure 3:

Building 39 (SVB) Site Figure 4:

Building 39 Floor Plan showing Areas to be Released Figure 5:

Location of Office Area and Matrix Room to be Released for Unconditional Use Figure 6:

Floor Scan in Office Area i

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$W FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 i

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Figure 6A:

Fixed Beta Measurements in the Office Area

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Figure 7:

Ceiling Scan in Office Area Figure 8:

Floor Exposure Rate Survey in Office Area Figure 9:

East Wall Inside Survey j

Figure 10:

North Wall Inside Survey Figure 11:

East Wall Outside Survey l

Figure 12:

North Wall Outside Survey

. Figure 13:

Roof Gravel Sample

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Figure 14:

Roof Tar Felt Survey j

Figure 15:

Roof Tar Felt Fixed Beta Survey

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Figure 16:

Roof Tar Felt Fixed Alpha Survey j

Figure 17:

Roof Insulation Scan j

Figure 18:

Roof Insulation Fixed alpha Survey j

Figure 19:

Metal Roof Surveys Figure 20:

Soil Sampling Locations for Office Area 2

Figure 21:

Matrix Room Surveys 3

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FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Introduction General Atomics (GA) is continuing its efforts directed at decontaminating, as appropriate, and obtaining the release to unrestricted use of selected facilities at General Atomics.

GA has recently completed the Final Radiological Survey of selected portions of Building 39, also known as Sorrento Valley "B" Building or "SVB", the " Fuel Pilot Plant Facility"or " Fuel Process Development Facility". The selected portions of the building to be released (not including walls) is ~9,700 ft and consists of the following:

2 1.

The Office Area concrete floor and associated structural walls (~4,700 ft ),

2 2.

the east end of the Matrix Room concrete floor (~300 ftz), and 3.

the metal roof over the office area (~4,700 ft ),

2 In addition, this report summarizes the Final Radiological Survey data for rekase of the following:

1.

The gravel removed from the roof, 2.

The tar and insulation removed from the roof, and The gravel, tar and insulation are currently being stored in dumpsters. The concrete slabs are being stored near the facility. These materials are being held until GA receives release to unrestricted use from the NRC, they will be disposed of to a bcal landfill after release is obtained.

This report documents the results of extensive and comprehen i te radiological measurements completed to demonstrate that these areas and materials meet the approved guidelines for release to unrestricted uss Site Description A plan view of the GA site is shown in Figure 1. Building 39 is located in GA's Sorrento Valley Site shown in Figure 2. Building 39 and the surrounding area is shown in Figure 3. Building 39 floor plan before decommissioning activities is shown in Figure 4. The floor plan for Building 39 showing the office area and matrix room area to be released to unrestricted use is provided in Figure 5.

The building is a square, one-story building which is 15 ft high and ~120 ft on a side for a total of 14,400 ft. The floor is a concrete slab which is nominally 6 in, thick. The building 2

exterior walls are constructed of concrete tilt-up slabs on the north and east sides and of sheet-metal on the south and west sides. The flat roof is a truss-supported sheet metal which was covered with an insulation layer, asbestos felt / tar, and gravel.

The office area is located on the north and cast sides of the building with exterior concrete walls. The total square footage of the office area floor and the roof above the office area to be released to unrestricted use is 4,700 ft2 each. The office area was separated from the operations area by a barrier wall of metal studs with drywall on each side of the stud wall. There was a 1

Ma*ve"s".'c4 FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 dropped ceiling 8 ft high made of standard ceiling tiles in the office area. Above the ceiling was a dead air space up to the 15 ft high roof.

The office area walls, roof, and Hoor are to be dismantled and disposed of as clean waste to the local landfill after release to unrestricted use is obtained.

The Matrix Room was added to the south end of the building. It consists of a concrete Door having an area of ~350 ft, and sheet metal walls and roof. The east end of the matrix room 2

(~300 ft of concrete floor) will be released to unrestricted use. The west end (~50 ft2 or 2

concrete floor) and the walls and ceiling will be disposed of as radioactive waste.

The roofing materials (gravel, tar and insulation) and the north yard concrete slabs have been removed from the building and surveyed and/or sampled to demonstrate that the release criteria have been met. These materials are currently being stored for survey and inspection by the NRC and/or the State of California prior to release to unrestricted use.

The rest of the building, which includes the fuel development processing area, will be dismantled and disposed of as radioactive waste. This includes the concrete floor, metal walls and metal ceiling. All equipment has been removed and properly disposed of. The Doors, walls and ceiling have been painted to fix any removable contamination.

Previous Activities (History of Use)

Building 39, has been used for the past three decades primarily to develop and optimize fabrication processes for the production of coated-particle fuel for HTGRs with funding for that work provided largely by the US DOE.

Large quantities of high enriched uranium (HEU), low enriched uranium (LEU), and depleted uranium and thorium were converted from conventional feedstocks into ceramic coated-particle nuclear fuel through a series of unit operations.

The office area was used as offices for the engineering and administrative staff. Two rooms, 107 and 111, were used as at dytical laboratories for examination of radioactive materials, uranium and thorium.

The east end of the matrix room was used for storage of non-radioactive materials and the west end was used for packaged radioactive materials.

Criteria for Release to Unrestricted Ues Facilities and Eauinment U.S. NRC's criteria for releasing facilities and equipment to unrestricted use is shown in Table Based on previous history of work conducted in this facility, the primary contaminants of concern for this site are uranium (HEU, LEU, natural, and depleted) and thorium. The applicable NRC guidelines for residual surface activity levels for uranium and thorium are:

2

,$W FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Uranium 2

2 5000 dpm WIO0cm, averaged over a 1 m area 2

2 15,000 dpm #100cm, maximum in a 100 cm area if the average over 1 m2 is met.

1000 dpm W100cm2, removable activity Thorium 2

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

2 3000 dpm/100cm, maximum in a 100 cm area if the average over 1 m2 s met 200 dpm/100cm, removable activity 2

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

dpm/100cm2 should apply to both alpha and beta measurements, independently, for surface contamination involving natural thorium. ( " Interpretation of Thorium Surface Decontamination Limits," U.S. Nuclear Regulatory Commission, February 9,1992). Thorium emits alpha radiation to beta radiation in a 1:0.67 ratio; therefore,1fbeta radiation measurements are being used to demonstrate compliance with the release criteria, the corresponding average and maximum beta activity guidelines were adjusted to be 670 dpm/100cm2 and 2000 dpm/100cm2, respectively.

Exnosure Rate Guideline The guideline value for exposure rates measured at I m above the surface, is 10 gR/hr above bac) 'round levels.

Soil reuse Criteria The soil release criteria also apply to concrete rubble, asphalt rubble and gravel. The release criteria (which are concentrations above background levels) for radionuclides used in Building 39 are as follows:

Thorium (Th-228 + Th 232) 10 pCi/gm Enriched Uranium (U-234 + U 235) 30 pCi/gm Depleted Uranium 35 pCi/gm if more than one radionuclide exists, the sum of the fractions of the concentration is calculated a= follows:

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M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Instrumentation l

Table 3 lists the instruments used during the radiological surveys. The table includes: (1) a i

description of the instrument, the model and serial numbers, (2) a description of the detector (If applicabic) and its serial number, (3) instrument ranges, (4) calibration due dates, (5) typical efficiencies, and (6) typical background count rates. All instruments used were calibrated semiannually and after repair except for exposure rate meters which were calibrated 4

quarterly.

Background Measurements Instrument Background Measurements 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 use or storage of radioactive materials in Building 13, (2) the various surfaces found in Building 39 could also be found in Building 13, and (3) the age of the building closely approximates the age of Building l

39.

d The fixed background measurements are shown in Table 4. The mean and standard deviation for each surface surveyed with the 100 cm detector were calculated using equations 8-11 and 2

8-12 from NUIEG/CR 5849 as shown below:

Equation (8 11):

x = k"', x, n,

Equation (8-12):

D., (x -x,)8 8"=h n -1 Background measurements and minimum detectable activities (MDA's) for each type of surface and for various counting times are also provided in Table 4. Minimum detectable activities (MDA's) for each type of surface, were calculated using equation (5-2) from NUKEG/CR-5849 as shown below:

l 2.71 +4.65/B"x t Equat. ion (5-2)

DA=

(dpm/100cm A

txEx 100 Where:

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

E = cfficiency 2

A = area of the detector (cm )

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.fM FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 llackcround Soil Concentrations Typical background concentrations measured by gamma spectroscopy in soil near the GA site have been established (at the 95% confidence level) and are provided in Table 9 along with a description of the locations where these samples were taken. llackground gravei sample results are provided in Table 10.

Sposure Rate Backermind Typical exposure rate background for this site is about 15 lyhr measured at I m from the surface. This value enn be measured south of Iluilding 15 (an office building on the eastern portion of the GA site). Measurements taken offsite in 10 different locations over a period of a year also gave an average of about 15 IVhr measured at 1 m from the surface.

Decontaminatien Activities Process Area With the termination of process development activities in fluilding 39, a cleanup, decontamination, and radiation survey program began in early FY96. All of the operating equipment, laboratory equipment, office equipment, supplies, non-load bearing walls, dropped ceilings and various other materials contained within the building have been removed. These items and equipment were surveyed and released to unrestricted use or properly packaged and disposed of as radioactive waste following routine IIcalth Physics procedures. All radioactive waste is being shipped to the Nevada Test Site for disposal, a Department of Energy (DOE) site.

In the process areas, the concrete floor, remaining metal walls, and the underside of the ceiling were spray painted (with paint appraed for burial at the Nevada Test Site) to fix contamination and will be dismantled and processed as radioactive waste.

f Office Area In the office Area, the non-load bearing walls and the dropped ceilings were surveyed, removed, and disposed of as clean waste or radioactive waste following routine Health Physics procedures.

Office Area Concrete Floor Some portions of the carpet and tiles in several offices were surveyed and found to be contaminated above the release criteria. Rather than perform comprehensive surveys with hand-held instruments to define the exact size of the contaminated area, all of the carpets and 5

1

.$M FINAL RADIOLOGICAL SURVEYS OF SELEGES PORTIONS OF BUILDING 39 tile were removed and disposed of as radioactive waste.

During the original characterization survey, fixed contamination above the release criteria was located in one area of the hallway outside the doorway to former room 102. This area measuring ~3 ft by 8 ft was painted to identify it as being contaminated and is shown in Figure 6.

The carpet which was over this area of floor was also contaminated, and it was removed and disposed of as radioactive waste. The entire office area Hoor was aggressively decontaminated using a blastrac unit (which uses metal shot to abrade the concrete surface) to remove the mastic left after the carpets and tile were removed and to remove the radioactive contamination on the floor. Surveys following the decontamination operation measured only background levels of radioactivity.

Office Walls The office area interior and exterior walls on the east and north ends of the building were surveyed and no contamination was found.

Metal Roof The metal roof over the office area was surveyed for release to unrestricted use. No contamination was detected. The rest of the roof will be disposed of as radioactive waste.

Matrix Room The matrix room consists of a concrete floor having an area of ~350 ft, and sheet metal walls 2

of concrete Door) will be released to and roof. The east end of the matrix room (~300 ft2 unrestricted use. One small area (~50 cm ), was fcund to be contaminated above the release 2

criteria (~ 2500 dpm/100 cm2 beta). Decontamination of the spot was attempted, but the radiation level was only decreased to ~2000 dpm/100 cm2. The area was clearly marked and it will be cut out when the floor is removed and the contaminated section will be disposed of as radioactive waste.

The west end (~50 ft of concrete floor) and the walls and ceiling will be disposed of as 2

radioactive waste.

Final Survey Plans Obiectives and Resnonsibilities The objectives of the final survey plans were (1) to demonstrate that the average surface contamination levels for each survey unit were within the acceptable values for release to unconditional use, (2) to show that the maximum residual activity (" hot spot" area) did not exceed three times the average value in an area up to 100 cm, (3) that a reasonable effort was 2

6

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.kM FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 59 made to clean removable contamination and fixed contamination and (4) that the exposure rates in occupiable locations are less that 10 R/hr above background measured at 1 meter above the surface.

Survey plans were prepared for each of the areas based on the previous history and the classification of each area by its contamination potential.

The survey plans which specified the types of surveys to be performed and the locations where surveys were to be performed were developed based upon the physical characteristics of the area, the radioactive material used and the potential for contamination. The physical characteristics of the office area includes the consideration of vents, ducts, whether surfaces are painted or unpainted, overhead structures, floor coverings, etc. The plans followed the requirements stated in the GA Site Decommissioning Plan.

Types of surveys performed include scanning, exposure rate measurements, survey measurements (wipes and hxed measurements), and collection of soil samples and paint samples.

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

Classification of Areas Unaffected Areas included:

most of the offices and the hallway, the inside of the north and east walls, the outside of the east wall, most of the outside of the north wall, most of the metal roof.

Non-Suspect Affected Areas included:

Offices 101,107, and 111, the area of the north exterior wall nearest to the HEPA exhaust plenums, the corroded areas of the metal roof.

Suspect Affected Areas included:

The gravel on the roof, the felt tar layer of material on the roof.

7 m.

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 RESULTS OF THE FINAL SURVEYS Scanning General Scanning was performed in each area using both beta Door monitors and alpha Hoor monitors having a 434 cm2 gas flow proportional detector. In each area where tile and/or carpet was present, the tile and the carpet was scanned over 100% of the surface. After the tile and carpet were removed, the bare concrete was scanned 100% for the final survey.

The walls and the ceiling were also scanned with Hoor monitors. Depending upon the activity that had been conducted in the area, and the classification of the area, the walls were scanned from 25% to 100% of the surface, and the ceiling was scanned 50% for alpha and beta with the floor monitors.

Office Walle, The office barrier walls separated the production area from the office area as shown in Figure 6.

This wall was made of steel studs with drywall panels on each side. This office barrier wall was removed and disposed of as radioactive waste.

The outside office walls, which are the east and north structural valls for the building, are tilt-7 up concrete panels. The inside of these walls (see Figure 9 for ins de east wall and Figure 10 for l

inside north wall) were classified as Unaffected Areas. -The outside of the cast wall is also an A

Unaffected Area (Figure 11). About 50% of the lower walls (<2m) and 10% o the upper walls I

(>2m) were scanned for both alpha and beta activity.

Part of the outside north wall was an Unaffected Area and part of it was a Non-Suspect j

Affected Area (see Figure 12). In the Unaffected Area, about 50% of the lower walls (<2m) l and 10% o the upper walls (>2m) were scanned for both alpha and beta activity. In the Non-l Suspect Affected Area,50% (of the entire wall from the base to the top) was scanned for alpha and beta / gamma activity.

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The scan results were all within the normal background ranges for the inside east wall and the outside east wall (Figures 9 and 11, respectively) and the inside north wall (Figure 10). Some areas of the outside north wall (Figure 12) had elevated scan results (maximum of ~300 cpm above background); these areas were res-surveyed with hand held alpha and beta / gamma j

j probes and levels were found to be at or near background levels. Results are provided in the respective Ogures and in Table 5.

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.$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 One area found to be contaminated was decontaminated to background levels. The rest of the office area concrete floor was scanned. Elevated areas were checked with hand-held probes.

Readings were at or near normal background levels. The results are provided in Figure 6 and Table 5.

Ceilirm over Office Areas The ceiling was scanned over 50% of the surface (the underside of the roof ) and the results were at or near background levels (see Figure 7 and Table 5).

Roof The gravel on top of the roof was surveyed with hand-held GM pancake detectors and hand-held alpha detectors during removal of the llEPA exhaust piping. All areas with radiation measurements above the release criteria were surveyed and contaminated areas identified.

These areas were marked for removal as radioactive waste. A systematic five meter triangular sampling grid was marked off on the roof and gravel samples were taken at each grid point (Figure 13). A total of 69 gravel samples were taken and counted on the gamma ray spectrometer in the HP lab. The sample results were analyzed and after background was subtracted (see Table 10), all of the Building 39 gravel samples were below the release criteria, see Table 8 The gravel was removed with the contaminated gravel being placed in the radioactive waste and the clean gravel being stored for inspection by the NRC.

The felt-tar layer under the gravel was surveyed 100%, alpha and beta, with the floor monitors (Figure 14 and Table 5). Fixed beta measurements and fixed alpha measurements were taken.

The beta counts were each 2 minutes and the alpha counts were ~5 to 10 seconds. All contaminated felt-tar areas above the release criteria were marked and removed as radioactive waste along with the underlying insulation. The rest of the felt-tar layer was then surveyed.

The level were elevated (as high as 2600 epm), llackground measurements on tar-felt range between 1845-2253 cpm (see Table 4). Elevated areas were scanned with hand-held instruments and no contamination detected above background. The clean felt-tar was separated from the insulation, removed and is stored for inspection by the NRC.

Much of the insulation under the felt-tar layer was broken into small pieces during removal of the felt-tar and could not be surveyed 100%. Approximately half of the insulation was in large pieces that were surveyed 100% with the floor monitors and the other half of the insulation which was in small pieces was surveyed at least 50% or more with hand-held instruments (Figure 17). The survey results for the insulation were all at or near background levels and the insulation was removed and is stored for inspection by the NRC.

9

.$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 The Door monitors were used to scan the metal roof above the office areas (an unaffected area).

About 25% of the entire roof above the office areas was scanned but areas along the edges of the walls and areas showing signs of corrosion were scanned 100%; for both alpha and beta activity. All scans were at or near background levels (see Figure 19 and Table 5).

Fixed Measurements Fixed measurements were performed using a beta gas-Dow proportional counter having a 100 cm detector. The counting time for beta fixed measurements was two (2) minutes. Alpha fixed 2

measurements were taken using a hand-held 50 cm scintillation detector, with a counting time 2

of 5 to 10 seconds. For fixed measurements an appropriate background was determined for each type of surface and subtracted from the survey readings. The readings were converted to dpm/100 cm 2 using the efficiency of the detector.

The locations of the fixed measurements are provided in Figures 6A for the office area, Figure 9 for the east wall inside, Figure 10 for the north wall inside, Figure 11 for the east wall outside, Figure 12 for the north wall outside, Figure 15 and 16 for the tar-felt layer on the roof, Figure 18 for the roof insulation layer, Figure 19 for the metal roof, and Figure 21 for the matrix room. Some of the figures provide the results (in counts per 2 minutes); these values were converted to dpm/100 cm2 and provided in Table 5. The maximum fixed measurement was 367 dpnV100 cm,

2 Itemovable Contamination Surveys itemovable contamination measurements (smears) were performed on all surfaces including floors, walls, ceiling, and overhead structures (light fixtures, I beams, heating and air conditioning ducts, fire sprinkler systems, electrical conduits, etc).

2 cach, taken with m.asslinn Two types of smears were taken. Large area smears, ~2 to 6 ft cloths and counted with portable hand held beta / gamma and alpha detectors. Levels were all at or near background for both alpha and beta / gamma activity.

The second type of smear was taken with Whatman Filter Paper (4.7 cm2 diameter) by wiping an area of 100 cm2 These smears were counted in GA's Health Physics Laboratory using a Canberra 2400 low level alpha / beta counting system. The maximum smear result in dpm/100 cm2 for both alpha and beta are provided in Table 5 for each area. All smear results werc < 10 dpm/100 cm2 alpha and < l5 dpm/100 cm beta; well below the release criteria.

2 Paint Sampline A total of 29 paint samples were collected on the inside and outside of the cast and north walls 10

.$W FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 (see Figure 9,10,11 and 12 for approximate locations). The paint samples were analyzed by gross alpha / beta counting. The highest result was 277 beta dpm/100 cm2 at location Pf, (see Figure 10). All alpha results werc < l5 dpm/100 cm2 At each location where a paint sample was collected, a 2 minute fixed beta measurement was taken before and after paint removal.

The results were all < 287 dpm/100 cm2 before and after paint removal. See Table 6 for the results of the fixed radiation measurements and the gross alpha / beta on the paint samples.

Exposure Rate Measurements Eleven (11) direct radiation exposure dose rate measurements were taken in the office area.

The measurements were taken at contact and at one meter above the surface. Measurements ranged from 17 -19 pR/hr (see Table 5 and Figure 8).

Soil Samples Soil samples were collected from seven (7) locations underneath the concrete Door in the office area (Figure 20). A surface (0-6") and a subsurface (6" 12") soil sample was collected from each location. All sample results were below the criteria for release to unrestricted use (see Table 7).

Matrix Room Survey The matrix room is a metal shed added to the south side of the building (Figure 21). The walls and roof will be disposed of as radioactive waste. The west end of the floor is contaminated and will be disposed of as radioactive waste. The east end of the floor was scanned 100% alpha and beta / gamma. Large area smears were taken in each quadrant and eight 100 cm smears were 2

taken. Fixed alpha and beta measurements were taken. All radiation measurements were at or near background levels (see Figure 21 and Table 5).

1 CONCLUSION Final surveys provided in this report, demonstrate that the following areas meet the approved guidelines for release to unrestricted use.

1.

The Office Area concrete floor and associated structural walls (~4,700 ft ),

2 2.

the east end of the Matrix Room concrete floor (~300 ft ), and j

2 3.

the metal roof over the office area (~4,700 ft ),

2 In addition, this report summarizes the Final Radiological Survey data for release to unrestricted use (offsite local landfill) of the following:

1.

The gravel removed from the roof, 2.

The tar and insulation removed from the roof, and 11

.$ W FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 2

Table 1:- USNRC'S ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclides

' Averaged Maximum"

Removable

h 8

2 2

(dpm/100cm )

(dpm/100cm )

(dpm/100cm )

U.nat, 2"U, 8U, & associated decay 5,000 e 15,000 a 1,000 a products Tra nsu ranics, 22'Ra, 22'Ra, 23+rh, 22*Th, 100 300 20

sipa,227Ac, insg, i29j Th nat, 2Th, "Sr, 22'Ra, 22*Ra, 2"U, i2'i, 1,000 3,000 200 ing,isig Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except ".Sr and other noted above.

a Where surface contamination by both alpha and beta / gamma emitting nuclides exists, the limits established for alpha and betdgamma-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 bacliground, efficiency, an geometnc 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 lhe maximum contamination level applies to an area of not more than 100 cnf.

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 shoutit not exceed 0.2 mRadhr 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.

' Guidelines For Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses For byproduct, Source, or Special Nuclear Material, USNRC, July 1982, incorporated into GA's SNM 696 license.

i 12

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Table 3:

List of Instruments Instrument Detector Range Calibration Efficiency Background (CPM)

Description Due Date Ludlum Ludlum Model 43-37 gas Four Linear I l-03-98 0 = 21.85%

Varies according to surface Active Probe Area = 434 cnf. The detector and RATE Model 2221 Proportional (434 cnf) Beta Ranges 02-17-99 p = 23.26%

being scanned.

METER are combined and mounted on a roll around cart detect r 0 -500.000 &

4n Sr-90 See Table 4 he instrument features a static-flow sptem, quick S/N 73701 S'N 094119-086265 One leg 50 -

connects, a portable gas bottle and a means to adjust the 500,00013 height of the detector from the floor for opt %um performance.

Ludlum Ludium Model 43-37 gas Four Linear 07-08-98 p= 22.84%

Varies according to surface Active Probe Area = 434 crd, he detector and RATE Model 2221 proportional (434 ad) Beta Ranges 01-06-99 p = 22.84%

being scanned.

METER are combined and mounted on a roll around cart detect r 0 -500.000 &

4x Sr-90 See Table 4 The instrument features a static-flow sptem, quick S/N 86302 S/N 086215 One Log 50 -

connects, a portable gas bottle and a means to adjust the 500.000 height of the detector from the floor for optimum performance.

Ludlum Ludlum Model 43-37 gas Four Linear 01-07-99 0 = 22.04%

Varies according to surface Active Probe Area = 434 crd. He detector and RATE Model Proportional (434 crd)

Ranges being scanned.

METER are combined and mounted on a roll around 222i Beta detector 0 -500.000 &

See Table 4 cart. Le instrument features a static-flow sptem.

S/N 086213 One Log 50 -

quick connects a portable gas bottle and a means to S/N 84459 500.000 adjust the height of the detector from the floor for optimum performance.

Ludlum Ludlum Model 43-37 gas Four Linear I l-05-98 a = 21.43%

Varies accordmg to surface Active Probe Area - 434 cnf. Le detector and RATE Model Proportional (434 crd)

Ranges 02-04-99 a= 22.37%

being scanned.

METER are combined and mounted on a roll around AI ha detector 0 -500,000 &

4 n Th.230 See Table 4 cart. The instrument features a static-flow system, P

a2221 S/N 079589 - 147965 One Log 50 -

quick connects. a portable gas bottle and a means to S/N 97817 500,00013 adjust the height of the detector from the floor for optimum performance.

Ludlum Ludium Model 43-37 gas Four Linear i1-28-98 a = 21.79%

Varies according to surface Active Probe Area = 434 crd. The detector and RATE Model 2221 Proportional (434 cnf)

Ranges being scanned.

METER are combined and mounted on a roll around AI ha detector 0 -500,000 &

4n Th-230 See Table 4 cart. The instrument features a static-flow system.

P S/N 148445 S/N 147966 One Log 50 -

quick connects, a portable gas bottle and a means to 500,00013 adjust the height of the detector from the floor for oprimum performance.

13

$M FIF ' RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Table 3:

List l of Instruments Instrument

. Detector J Range Calibration Efficiency Background (CPM) i Description '

nue nate Ludlum.

Ludlum Model 43-68 Four linear I l-28-98

$ =26.09%

Varies according to surface 100 cm2 gas flow proportional counter.

Model 2221 100 cm2 proportional ranges 04-12-99

$ =26.40%

being scanned.

Beta counter SN 142547 0 -500.000 &

4x Sr 90 See Table 4 S/N 148425 log 50 -

500.000 Ludlum Ludlum Model 43-68 Four linear 08-04-98 p =25.04%

Varies according to surface 100 cm2 gas flow proportional counter.

Model 2221 100 cm2 proportional ranges I l-03-98 p =27.06%

being scanned.

Beta counter SN 120477 0 -500.000 &

4x Sr 90 See Table 4 S/N 148436 one log 50 -

500.000 Ludlum RCA 6199 coupled to a Nal Five Ranges I l-03-98 N/A

!O-18 pR/hr I inch X 1 inch Nal (71) scintillator is mounted internally.

Model 19 (TI) Scint:11ator 0-5 mF/hr pR Meter Used for measurmg external dose rates on the surface and

• '"'I'**'

S/N 87120.

Ludlum Ludlum Model 43-65 Four ranges 01-19-99 a = 21.58%

0-20 Active Probe Area = 50 cm2

^! ha Sdntillator 0-500,000 4x Th-230 Used for alpha surveying.

Model 12 -

P S/N 91051 ZnS(Ag) S/N 094053 Ludlum Ludlum Model 43-65 Four ranges 10-12-98 a = 21.25 %

0-20 Active Probe Area = 50 cm2 AI ha Scintillator 0 -500,000 4x Th-230 Used for alpha surveying.

Model 12 -

P S/N 99410 ZnS(Ag) SW il7842 Ludlum.

Ludlum Model 44-9 Four Ranges 10-20-98 p =25.58%

60-100 Active Probe Area = 15 cnf Model 3 beta / gamma probe 0 -100,000 4n Sr 90 Used for beta' gamma sunging.

S/N 46465 S/N 089925 Ludlum Ludlum Model 44-9 Four Ranges 11-27-98 p =23.24%

60-120 Active Probe Area = 15 cni W

2"" Probe 0 - 100.000 4x St-90 Used for beta / gamma sumying.

Model 3-8 S/N 139180 SW 145973 l

14

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'$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Table 4: Background Measurements and MDNs 100 cm2 beta detector - measurements done 08/20/98 and 11/24/98 Model 2221 ratemeter s/n 148425 probe s/n 142547 (efficiency 26.09%)

llackground Material Average of 10 measurements.

MDA 2

. (2 minutes each) totalcounts 1SD (dpm/100 cm )

Concrete 1026 66 287 hietal 789 19 253 Asphalt 1561 24 353 100 cm2 beta detector measurements done 05/07/98 and IW23/98 Model 2221 ratemeter s/n 148436 probe s/n 120477 (efficiency 27.06%)

Background Material Average of 10 measurements MDA 2

(2 minutes each) total counts

!SD (dpm/100 cm )

Concrete 933 19 268 Concrete Illock 802 14 249 Drywall 510 151 199 Metal 575 14 213 Wood 719 30 236 Gravel over tar 1156 56 297 and insulation 100 cm detector used in scanning mode 2

Gravel over tar 516-630 beta / gamma range in epm na 2

434 cm Floor Monitor Background Scan Results Surface Beta / gamma Scan Range Beta / gamma Scan Range Beta / gamma Scan Rr.nge (cpm) s/n 73701 done (cpm) s/n 86302 done (cpm) s/n 84459 done 4/13/98 and IW20/98 4/14/98, i 1/10/98 and 4/22/98 12/07/98 Concrete 1795-2030 1276-1530 1400-1570 Concrete block

!281 1554 1253-1538 1174-1409 Drywall 906-1050 693 951 770-937 Metal 1151 1425 853 1185 816-1047 Linoleum over 867-1134 Concrete wood 915 1244 asphalt 1261-2530 16

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Table 4: Background Measurements and MDA's 8

434 cm Floor Monitor Background Scan Results

' Surface Beta / gamma Scan Range Beta / gamma Scan Range Beta / gamma Scan Range (cpm) s/n 73701 done (cpm) s/n 86302 dune -

(cpm) s/n 84459 done 4/13/98 and 10/20/98 4/14/93 4/22/98 tar / felt, 2104-2253 1845-2148 insulation (taken on roof of Building 10) 8 434 cm Alpha Floor Monitor Background Scan Results (cpm) s/n 148445 and s/n 97817 Range from 0-20 cpm (all surfaces) l i

i l

17

- - _.. =..

i

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39

~

~

Table 5i Results of Surveys in Building 39 Office Area and Matrix Room -

Fixed Measurements '

dpm/100 cm2 100 cm2 Smears a Scan Results p Scan Results Fig -

Location 434 cm '

434 cm2 p

Results 2

a

@sure Dose h -

No.

and Surface.

(cpm range)

(cpm range)

(50cm.

(100cm2 dpnt'IOO cm2 Measurements '

2 detector).

detector)

N ')

g Alpha.

Beta t

Office Area 6

Concrete Floor 10 -16 1950-2150 22

<10

<15 Scans and Smears Office Area Concrete Floor

<MDA 6A

~

~

~

(<287)

Fixed Measurements Office Area 7

Ceiling 6-11 1098-1231 22

<10

<15 Scans and Smears Office area Concrete 17 - 19 gIVhr Surface 8

Floor 17 - 18 plVhr 1m above Exposure Dose Rates surface East Wall Inside

<MDA 9

Scans, Smears, and 10-20 1675-1800 12

(<287) 20

<10

<l5 Fixed Measurements North Wall Inside 10 Scans, Smears, and 8 - 15 1700-1950 12 87 20

<10

<15 Fixed Measurements 18 i

~.

k "mrummes FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 I

Table 5: Results'of Surveys in Building 39 Office Area and Matrix Room.

Fixed Measurements dpnV100 cm2 100'cm2 Smears a Scan Results p Scan Results Fig :

. Location 434 cm.

434 cm2 n'

D Results..

2 Exposure Dose Rate'.

No.

and Surface.

(cpm range).

(cpm range)

- (50cm2 (100cm2 -

' dpnV100 cm2 Measurements detector) detector)

Alpha Beta -

N)

East Wall Outside

<MDA 11 Scans, Smears, and 8 - 16 1657-1922 12 I#

)

20

<10

<15 Fixed Measurements North Wall Outside

<MDA 12 Scans, Smears, and 10 -30 1600 2100 25

(<287) 35

<10

<l5 Fixed Measurements 0-40 1800-2200

'***I (50-300 (2000-8,000 13 Scans (samples' contaminated contaminated see TaNe 8) to rad. waste) to rad. waste) 0-40 1400-2600 (0-300 (3000-20,000 14 Roof Tar-Felt Scan

~

~

~

~

~

'~

~

contaminated contaminated to rad. waste) to rad. waste)

Roof Tar-Felt Fixed

<MDA 14

~

~

~~

(<287)

~

~

~

~

Beta Measurements Roof Tar-Felt Fixed 20-40 15 116

~

~

~

~

~

l g

(~bkgd) 19

$ ",",e"mm"e",

FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Table 5: Results of Surveys in Building 39 Office Area and Matrix Room Fixed Measurements dpm/100 cm2 100 cm2 Smears a Scan Results p Scan Results Fig-Location 434 cm2 434 cm2 a

P Results 1 Exposure Dose Rate No.

and Surface (cpm range)

(cpm range)

(50cm2

. (100cm2 dpm/100 cm hieasurements 2

detector) detector) '

N) g Alpha Beta Roof Insulation Scan Scan 434 cm2 beta 2

Both 434 cm2 434 cm =

^"C*

17 and 50 cm2 =

1400-1500.

Alpha Scan both 0-40 GM = 40-80 434 cm2 and 50 cm2 detectors Roof Insulation 20-40 18 Fixed Alpha 116

~

~

(~ Bkgd)

Measurements Metal Roof DA 19 Scans, Smears, and 0-41 924-1387 35

(<235) 50

<20

<20 Fixed Measurements Matrix Room Concrete Floor 0-20 22 Scans, smears, Fixed 0-50 1200-1400 17 367 8

<10

<l5 13 at I m above surface B@

Measurements and Exposure Dose Rates 20

MM FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 TABLE 6: PAINT SAMPLE RESULTS Sample Paint Sample Results Fixed Measurements Number -

dpm/100 cm2 2 minute count with 100 cm2 beta detector 2

dprn/100 cm 3

Alpha

' Beta -

Before Paint Sample After Paint Samp i

Figure 11: East Wall Outside Building PA

<10 71

<MDA (<287)

<MDA (<287)

PB

<10 57

<MDA (<287)

<MDA (<287)

PC

<10 81

<MDA (<287)

< MDA (<287)

PD

<10 46

<MDA (<287)

<MDA (<287)

PE

<10 33

<MDA (<287)

<MDA (<287)

Figure 10: North Wall Inside building PF

<15 277

<MDA (<287)

<MDA (<287)

PG

<10 40

<MDA (<287)

<MDA (<287)

PH

<10 88

<MDA (<287)

<MDA (<287)

PI

<10 25

<MDA (<287)

<MDA (<287)

PJ

<10 60

<MDA (<287)

<MDA (<287)

Figure 9: East Wall Inside PK

<10 63

<MDA (<287)

<MDA (<287)

PL

<10 48

<MDA (<287)

<MDA (<287)

PM

<10 61

<MDA (<287)

<MDA (<287)

PN

<10 96

<MDA (<287)

<MDA (<287)

PO

<10 72

<MDA (<287)

<MDA (<287)

Figure 12: North Wall Outside PP

<10 75

<MDA (<287)

< MDA (<287)

PQ

<l5 46

<MDA (<287)

<MDA (<287)

PR

<l5 136

<MDA (<287)

<MDA (<287) 21

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 TABLE 6:' PAINT SAMPLE RESULTS.

Sample Paint Sample Results Fixed Measurements Number--

dpm/100 cm -

2 minute count with 100 cm beta detector 2

2

~

dpm/100 cm2 Alpha Beta Before Paint Sample After Paint Sample PS 15 53

<M DA (<287)

<MDA (<287)

PT

<l5 67

<MDA (<287)

<MDA (<287)

PU

<15 55

<MDA (<287)

<MDA (<287)

PV

<l5 52

<MDA (<287)

<MDA (<287)

PW

<15 57

<MDA (<287)

<MDA (<287)

PX

<l5 150

<MDA (<287)

<MDA (<287)

PY

<l5 46

<MDA (<287)

<MDA (<287)

PZ

<15 45

<MDA (<287)

<MDA (<287)

PAA

<l5 81

<MDA (<287)

<MDA (<287)

PBB

<l5 65

<MDA (<287)

<MDA (<287)

PCC

<l5 85

< MDA (<287)

<MDA (<?87) l 22

hM FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Table 7: Soil Sample Results from Underneath Office Area Floor Radionuclide Concentration (pCi'gm) -

238 Sample U

2"U "Th.

22 Ra-ID-Average of -

(2nIh)

Total and depth -

92.77 kev peak Error 186 (144) kev peak Error 583/238 kev peaks Error Average of Error Thorium 583/238 kev neaks h-Soil OSI 0-6" 0.98 37 ND 0.92 15 1.05 31 1.60 Soi10S1 6*- 12" 2.00 37 ND 1.14 10 1.77 26 2.91 Soil OS2 0-6" 1.67 31 0.12 48 0.67 11 1.08 24

'.75 Soil 052 6*- 12" 1.63 34 0.08 59 0.68 12 1.21 19 1.89 Soil 053 0-6" 0.57 90 0-.52 119 0.41 22 1.01 40 1.42 Soil OS3 6"- 12" 2.00 33 0.92 45 0.88 15 1.63 27 2.51 Soil 054 0-6" 0.98 60 0.56 95 0.39 25 0.62 40 1.01 Soil 054 6"- 12" 2.02 28

0. I 1 40 0.08 11 1.17 25 1.96 Soil OSS 0-6" 1.02 51 ND 0.54 14 1.09 29 1.63 Soil OS5 6"-12" 1.54 36 0.18 41 0.87 14 1.28 30 2.15 Soil OS6 0-6" 1.37 56 0.17 56 0.92 11 1.71 22 2.63 No subsurfacesample l

Soil OS7 0-6" 0.85 51 0.09 57 0.42 16 1.24 I8 2.01 Soil OS7 6"- 12" l.76 25 0.11 43 0.77 10 23

i.

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF Bull. DING 39 g7a g ggggg agigop3gR3ef Giavel Sample RAshi@ Wi w - @$s#;

~

Sum of the NET SUM OF FRACTIONS Sample No.

U-235 U-238 Total Th Fractions

[ Sample Sum minus pCi/gm pCi/gm pCi/gm Bkgd. Sum (0.37)]

G-01 0.29 2.91 4.41 0.81 0.44 i

G-02 0.29 2.38 3.14 0.69 0.32

c G-03 0.33 3.1 5.0 0.92 0.55 w

G-04 0 35 3.23 5.41 0.98 0.61 G-05 0.32 3.33 3.49 0.76 0.39 G-06 0.36 ND 3.24 0.68 0.31 G-07 0.23 2.04 4.31 0.72 0.35 G-08 0.21 5.53 6.76 -

1.04 0.67 G-09 0.43 4.31 4.35 0.99 0.62 G-10 0.28 3.16 4.2 0.79 0.42 G-11 0.36 3.33 4.40 0.89 0.52 G-12 0.18 3.65 5.6 0.84 0.47 G-13 0.23 3.30 4.73 0.80 0.43 G-14 0.28 2.51 6.I3 0.96 0.59 G-15 0.26 2.98 5.71 0.92 0.55 G-16 0.26 3.96 3.65 0.74 0.37 24

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39

,y

,, !Tn16T8?LBhildingW9106f G)svellsimplEREsulls)

~

Sum of the NET SUM OF FRACTIONS Semple No.

U-235 U-238 Total Th Fractions (Sample Sum minus pCi/gm pCi/gm pCi/gm Bkgd. Sum (0.37)]

G 17

0. I 7 2.32 4.95 0.73 0.36 G.I 8 0.27 3.00 3.28 0.68 0.31 G 19 0.32 4.38 5.05 0.95 0.58 G 20 0.15

3. I 8 4.80 0.72 0.35 G-21 0.25 3.04 3.04 0.64 0.27 G 22 0.35 2.97 3.90 0.79 0.42 G-23 0.34 3.73 4.80 0.92 0.55 G-24 0.31 3.55 3.21 0.73 0.36 G-25 0.30 3.54

3. I 6 0.72 0.35 G-26 0.22 2.92 5.34 0.84 0.47 G 27 0.24 4.50 4.98 0.87 0.50 G-28 0.24 3.28 4.88 0.82 0.45 G 29 0.31 3.50 4.27 0.84 0.47 G-30 0.33 3.39 3.59 0.78 0.41 G 31 0.39 3.20 5.60 1.04 0.67 G-32 0.29 2.87 3.73 0.75 0.38 G-33 0.27 3.50 3.02 0.67 0.30 l

G-34 0.31 4.34 3.45 0.78 0.41 G-35 0.28 3.25 5.19 0.89 0.52 G-36 0.17 2.86 4.80 0.73 0.36 G-37 0.28 3.36

3. I 1 0.69 0.32 i

G-38 0.20 3.80 3.05 0.61 0.24 G-39 0.19 3.21 5.35 0.81 0.44 G-40 0.39 3.45 3.38 0.83 0.46 25

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39

^

py gggg-6Budhg39 RMf Giavel SdmplERessidi a

Sum of the NET SUM OF FRACTIONS Scmple No.

U-235 U 238 Total Th Fractions

[ Sample Sum minus pCi/gm pCi/gm pCi/gm Bkgd. Sum (0.37)]

G 41 0.48 3.37 5.23 1.10 0.73 i

G 42 0.35 3.33 2.94 0.74 0.37 G-43 0.41 3,05 5.25 1.02 0.65 G-44 0.21 2.80

3. I 3 0.60 0.23 G-45 0.46 3.35 4.82 1.04 0.67 G 46 0.20 3.23 3.34 0.63 0.26 G 47 0.32 4.1 ",

3.57 0.79 0.42 G-48 0.43 3.36 3.46 0.87 0.50 G-49 0.31 3.06 5.64 0.96 0.59 G-50 0.23 3.12 2.76 0.59 0.22 G-51 0.29 2.23 3.37 0,69 0.32 G 52 0.29 3.44 5.47 0.94 0.57 G-53 0.35 4.19 3.45 0.81 0.44 i

G-54 0.27 2.90 4.99 0.85 0.48 1

G-55 0.37 3.91 6.47 1.13 0.76 G-56 0.20 2.57 4.87 0.76 0.39 G-57 0.26 2.73 4.77 0.81 0.44 G-58 0.19 3.76 3.40 0.64 0.27 G 59 0.32 3.35 3.74 0.79 0.42 G-60 0.32 3.58 3.69 0.79 0.42

}

5.14 0.92 0.55 i

G 61 0.33 2.7't G 62 0.24 3.3 i 3.07 0.64 0.27 G-63 0.20 ND 4.51 0.65 0.28 i

G 64 0.24 3.22 3.45 0.68 0.31 26

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39

!LTsblE8!lBsilding 39;RS6f Gisvel SamplSIR$sunst

< ee

• W

+

m, Sum of the NET SUM OF FRACTIONS Simple No.

U 235 U-238 Total Th Fractions

[ Sample Sum minus pCi/gm pCi/gm pCi/gm Bkgd. Sum (0.37)]

G-65 0.22 2.47 2.47 0.54 0.17 G-66 0.30 3.07 5.19 0.91 0.54 G 67 0.48 3.30 5.39 1.11 0.74 G-68 0.30

3. I 7

3. I 8 0.71 0.34 G-69 0.35 2.89 4.68 0 90 0.53 Average 0.12 1.35 2.09 0.37 Brckground I

1 27

$M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDING 39 Table 9: Background Soil Sample Results 2 Total

' Sample -

- r Cs 137

' Th 228

' Ra-228 Thorium

.U-238 '

U 235 '

2

. ID ~

- (Th-232)

Th 228 +

Th-232 Radionuclide Concentrations (pCi/g)

AJ ND 1.28 0.07 1.47 0.14 2.75 1.98 0.31 0.15 0.03 G2 0.12 0.03 0.92 0.07 1.01 0.12 1.93 1.86 0.29 0.12 0.02 AC ND 1.29 0.07 1.34 0.14 2.63 2.27 0.27 0.20 0.03 BKG-1 ND 1.4010.16 1.44 0.28 2.84 2.06 0.48 0.19 0.06 i

BKG-2 ND 1.54 0.15 1.57 0.27 3.11 2.30 0.45 0.17 0.05 i

BKG-3 ND 1.40 0.14 1.62 0.26 3.02 ND 0.19 0.05 BKG-4 ND 0.67 0.09 0.84 0.17 1.51

1. I 5 0.37 0.09 0.04 BKG 5 ND 1.51 0.16 1.79 0.31 3.30 2.77 0.67 0.12 0.06 BKG-6 ND 0.68 0.09 0.76 0.16 1.44 ND 0.08 0.03 _

BKG 7 ND 1.17 0.12 1.28 0.22 2.45 1.83 0.43 0.11 0.04 Mean z 2 a 1.19 0.64 1.31 0.68 2.5 1.32 2.03 0.93 0.14 0.09

' Samples gamma scanned for I hour.

ND=

< 0.1 pCi/g for Cs-137, < l.0 pCi/g for U-238 8 Sampla collected in June and August 1993, typically about 12 miles from the Building 37 site at the following locations:

Al 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 Building 37.

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

BKG-1 Collected about I mile from Building 37 at the Scripps Hospital Entrance, cast 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 Pines Road and Torrey Pines Scenic Drive 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) 28

+M FINAL RADIOLOGICAL SURVEYS OF SELECTED PORTIONS OF BUILDlNG 39 Table 10: Background Gravel Sample Results (Gamma Spectroscopy, 30 Minute Count Times)

' (S2mnles Cntlected from Bull linec 10. 33-l'nnd 333 Radionuclide Concentration (pCilg) - Results 2 SD Sample ID Cs "Co 22sTh 22e Ra Total Thorium assU 235 "7

U Average of I173 and Average of (2s2Th) 661.6 kev peak 1332 peaks 583/238 kev peaks Average of 2:sTh + 232Th 92.77 kev peak 186 (144) kev 91R911 kev nenk e nesk BIO-Roof-l G ND ND 0.26 0.04 0.45 0.14 0.71 0.88 z 0.27 0.06 0.03 B10-Roof-2G ND ND 0.25 0.06 0.5I t 0.21 0.76 1.03 0.40 0.06 0.04 B10-Roof-3G ND 0.02 0.02 0.27 0.06 0.37 0.24 0.64 0.81 0.51 0.05 0.04 B10-Roof 4G ND ND 0.32 0.08 0.73 0.37 1.05 ND 0.06 0.06 BIO-Roof-5G ND ND 0.35 0.09 0.77 0.33 1.12 0.70 0.50 0.10 0.07 B33-1-Roof-6G 1.10 0.10 ND 1.07 0.11 1.77 0.34 2.84 2.77 0.56 0.17 0.09 B33-1-Roof-7G 0.91 0.13 ND 3.01 0.35 1.81 0.43 4.82 2.41 0.70 0.27 0.12 B33-1-Roof-8G 1.09 0.10 ND 1.05 0.10 1.74 z 0.33 2.79 2.73 0.55 0.17 0.09 B33-1-Roof-9G 0 98 0.09 ND 2.55 0.28 1.66 0.35 4.21 1.77 0.43 0.27 0.07 B33-I-Roof-10G 0.87 0.09 ND 2.89 0.27 1.53 0.31 4.42 2.50 0.57 0.18 0.08 B33-Roof-lG ND ND 0.50 0.11 1.01 0.40 1.51 0.8720.62 0.13 0.09 B33-Roof-2G ND 0.04 0.05 0.50 0.10 1.05 0.41 1.55 0.72 0.58 0.10 0.08 29

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FIGURE 2: SORENTO VALLEY SITE m. -i U

. m m

i 1

.)

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~

^

PLOT PLAN SCALE GAS FARM I

WI FT

,a

'x n

S.V."8" 5

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m STORAGE SHED W

m E

COMPRESSED GAS

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STORAGE g

BUILDING 37N FORMER SITE l

w l

1; 4-BAY STORAGE BUlt. DING.

g i

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l 01

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=

g l

5 s

'I am 7

=_ %

Y 7

~

m g

( T_,

t

. FIGURE 4: BUILDING 39 FLOOR PLAN J

c.

1 FIGURE 5: LOCATION OF OFFICE AREA AND MATRIX I

ROOM TO BE RELEASED TO UNRESTRICTED USE.

i.

A B

C D

E F

i d

Process l

3 L

areas i

i i

4 t

r i

\\

l 5

l Noe 1

>,: c : ;..

A ;.m - >. ~.'? = l

a:.

s, p L, -

.,i,

N

.. idd

~

'-+

5 4 k i: @. #.% % }f..,G,, $

)

l

.=

(

l l

FIGURE 6: FLOOR SCAN IN OFFICE AREAS A

B C

D E

F i

__M M

i Notes:

initial surveys detected contamination in only one area on the floor i

outside room 102. The area was marked, painted and 1

decontaminated to background levels.

Grid Entire office area was scanned with 434cm' floor monitors. Areas I

with high readings were checked with hand held meters.

Locators Large area wipes were taken over the entire area. Results were at background levels for alpha, and beta, gamma.

2 l

i Legend:

i 3

= # cpm / probe area. Alpha (a) and beta, gamma (bg).

'{M = Office areas I omwww l\\\\\\\\\\\\ u Contaminated 4

= smear prOCOSS areas 5

1000 com/orobe area. beta. aam.ma 600 com/ probe area. alpha l

NoHh "N

~n 6

h+

t e-l l

I h

I FIGURE 6A: FIXED BETA MEASUREMENTS IN OFFICE AREA 1

A B

C D

E F

i M

M

[--

n 749 7

- 'l MAgf -

1 q

.~

m

^

4 m

n j

1"' g 2

i s.

m Legend:

)

Rilmmela!!

kh

1. [!

= Total counts in 2 min.

URR/d 3

fixed 100cm2 probe E. n9Alf

= Office areas nWM C

[k

~

718 M

I$

'M

,.f[

h KT Mfkf 4

Process 1

a areas

?

4 k h' ffs*E 13 f.)P BI.jd4f6ph;,[4 6-5 N

.g

<g z

a l

u s

w t,4s1. '

If y" t m

p g l u u m u q u

- 4p 4 5

,) g$a.i J.

1

• a #

8 th m

p em 1

=

i m

.s?

=

1

,gt y

n.n L;

c rr 1

' +

a -

P !

! !- Hm m H

ik W 1

w m

m s

a

{

i i

FIGURE 7: CEILING SCAN IN OFFICE AREAS l

A B

C D

E F

4 l

m l

Notes:

50% of the ceiling in the office area was scanned with i

434cm floor monitors for alpha and betargamma.

2 I

Areas with high readings were checked with hand held gjis

~ meters. No contamination was detected. Large area 2.j)pJig wipes were taken over the entire ceiling surface.

Results were measured with hand held meters and

'~

l' f und to be at background levels for alpha, and beta, 2

gamma.

7 4

Legend:

i 5 --

l

= # cpm / probe area. Alpha (a) and beta, gamma (bg).

3 l

an$ddi = Office areas

+

f

\\\\\\\\\\\\ = Contaminated 7

'Nh

= Smear Process

.s

~t~g-A area F

t,,o P,p i

$f 10

,g i

i i

i4 4,

. <., n

' $g, l jig, i3, ]{}fk 1

o-

. TW i i

g

l Figure 8: Exposure Rate Survey in Office Area j

A B

C D

E F

l m

l Notes:

37(s)

~

1 Exposure dose rate readings were taken 10ft apart 17(1m) down the center of the offices; on the floor surfaces (s) 3 and 1 meter above the surface (1m). The surface is j

concrete.

2 17(s) 17(im)

Legend:

• \\ Mh[

l i

= Ur/hr reading (s) = surface (1m)= 1 meter above the surface

. p'i 3

17(s)

I 17(im) -

$$ = Office areas 17(s) 4 Process 27(im>

areas d3 w t.c fS[g

~

17(s) 4 5

q 37(3,3 g l

North

! %g c

a-i

.- 5

. // i n,

?. g '

g L'1*

'j

{

17(s) 17(s) 17(s) 18(s) 17(s) 19(s) 6 17(1m) 17(im) 17(im) 17(im) 17(1m) is(im) j-4 TL

.c

Figure 9:

EAST WALL INSIDE RELEASE SURVEY

^

n 19j 10 %

9 8

8 $

8 8

8

,i i

i i

i i

l 962 l l toss l

^

6' l 920 l g

$$) [

[ 595 )

f 9((]

57]

l 897 l l 886 l y

v Panel #1 2

3 4

5 6

7 8

9 10-11 12 120' P

S pies SCAN AVERAGE cpm / probe Area Total counts in 2 min.

NOTES:

PANEL #

Alpha Beta / Gamma Before After O

1 10 1675 i

re al R

at 2

20 1700 panels. All readings were at 3

172s Pk a79 ins' 2g background levels.

S 0

1 PI can inv b

= PAINT SAMPLE 7

20 1800 Pm oss 1119

=gygggg

_, Total counts in 2 minutes 8

im0 2g

=

2 (100cm beta probe) 5 10 1725 pn Qat 1173 10 1700 52 20 1755 Pn 477 iina Scan Background 10-20 1600 -1800

FIGURE 10: NORTH WALL INSIDE RELEASE SURVEY

^

10 %

8 8

8 8

8 Scan

,"I I"I 1_9' i sou l l*l j ioc l j,- l 9

6' 100 %

g Ae A

ig A8 A@

Ae i-i i 4-i i -i i,_,

3

~

PaneI#

1 2

3 4

5 6

7 8

9 10 11 12 120' 4

PAINT SAMPLES 100cm Fixed Beta NOTES:

2 SCAN AVERAGE cpm / probe Area Total counts in 2 min.

PANEL #

Alpha Beta / gamma Before After l

Large area smears were taken on entire wall panel.

i 11.

1750 D

mm at m

at

5

,Psa__

9 2

Pf 975 1160 4

_ 14 1700 s

'8 1800 PG 969 1117 l

j = Total Counts in 2 minute 9

PH 1013 1101 l

}

I!b 2

Pi 990 1o85 (100cm beta probe) l

g

9g g = Paint Sample n

1

- 8s0 Pi 999 1090 h = Smear Scan Backaround 0 - 21 1762 - 2110

FIGURE 11: EAST WALL OUTSIDE RELEASE SURVEY a

n 8

8 10%

l1001l l ses l l 1027 l g

DR 8

8 i

.7.

i i,,, i i-i 19

^

e' 100 %

j og7 ;

d 1o12

j2o3, j

Scan gl=l g

l ses j s

is v

I v

Pcnel # 1 2

3 4

5 6

7 8

9 10 11 12 120' SCAN AVERAGE PAINT SAMPLES NOTES-cpm / probe area 100cm' Fixed Beta Alpha Beta / gamma nts in 2gn.

Large area smears were taken on each panel. All Large area -

ma PANEL #

smears were at background levels. Areas with elevated scan sample paint paint 1

10j y

10 r-'

ramd readings were checked with hand held instruments.

3 10-20 1804 Pa 988 1041 4

10 20 1703 10-20 in Pb 1001 1122

= Total counts 2 min. fixed O = smear g

7 10 20 1700 Pc 978 1023 100cm2 Beta probe 8

'O-20 1723 10 -

0 $0 E

= Paint Sample 11 10-20 1715 Pm 901 1088 12 10-20 1688 Scan Background 0-20 1711 -2004

F!GURE 12: NORTH WALL OUTSIDE Non-Suspect affected Area Unaffected Area i

i i

i i

i i

i i

i

)

)

^

n Inl l=l I"I b

b b

b h

as 10%

l=1 Iml l mi l Scan lel b l=l t ion l l-l 8

A I'"I b

O O

19'l L=J l-l t

b

k l as i 9

6' I

I"I M

___ k 100 %

k I en I

/eh,,

l=l n

l=l li=2l m

s e

b I"I b I"I b

b b

I"Ib b b

v v

Panel # 1 2

3 4

5 6

7 8

9 10 11 12 120' PAINT SAMPLES 100cm Fixed Beta Total counts in 2 min.

NOTES:

Scan Average Before After cpm / probe Area Sanple Paint paint Large area smears were taken on ent. ire wall panel.

PANEL #

Alpha Beta / gamma io removal removat All large area smears were at background levels.

3o.30 1800-1800 PR 1063 1048 Areas with elevated scan readings were checked with 900 1

l

gjg

'g "

lS hand held meters. All readings with handheld meters l

$$8

'E$"

$0

$7!

jg were at background levels. Smear # 20 didn't get a

' o-2n 1700 70n0

>w m't M

Counted.

$$!l 0,81$888 E

!Po L!E I

I

= Total counts in 2 min. Fixed

'Rj8

Q'"

A j,

if8 (100cm Beta probe) 2 iS$8

SSI$888 8$$

A

= Paint Sample l

PP 978 X)

A PO 1o11 1042 U

= Smear Scan Background 10-20 1700 -1800

. ~. -

I l

A B C D E FG H I J K L MNO P Q RS TU yw l

37 as G.

JJJJ in i I

3s

' ' 67oo cpm pi j j,j j [3 ] -

h

,1._l l

.'. m,m.

l 34 J.JJJJJJ-JJJJ JJJJ_SJJJJJJ~

g J J.JJ l

33 JJJJJJJ ij e

i J.4E l

==

High Bay

'l

(

i i

I.I J

3, I._I _I _lgt ~I t-2 O

l

~

l

_ _f I,,,1,_t _,,3,,,,g,_g ao g

_,,_g _g JJJJJJJJJJj-

'8-as I

I I I

O i i:

g JJJ0 m

_lJ J J _lJ I

l ~8_.I

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l J J _: j ~, ~~# ~# ~#

' d I J. J }

37

+L lfI i

ne l

I g

g l

- _ _ g l _ I _ I,1 _ t,,,i _ l J, a ce m n i

Gisoepm. _,

. l. _,

l 1

i f

i as

--.g

- ',j -g p 4

cpm Bl _,., J j,,g j j ' u_,

I I

1 a4 150 cpm a g'g -lJ J.J., %

,J ""jl l

23 l

l l l

$ 8000 cpm pi g

1 11jjj 22 l

l l

l 0 cpm a 1

I ei -i, J._.8. _I l

1 i

a, l

i

. O.

j

~, - ~ ',

l J J J.._.l_1.fJ._ J _s.- 1 l

~

i

' ~ ~' d

' 3 3 ~l ] ], ] ~s _~e ] ~ ~~i,' J l

,, d J J J. l. J.2t h l-8 is JlJJ

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1 i

4 a

r J J J lJ.J._l+1 9J i sj ~i.J J 9

n

_l.J _I _

._ y is

4. ' J _,

JJJlJJ l

_T_1 e

dJJJjJ is

~ ~ ~I 2000 4000 cpm sr

• • N I

I 14 l

jjj[

e so m cym.

,3, g.

e J J J J jlp i,

I I I i

,e i

si

>JJjaa_,m

,J.J J l-J _

~"J28JJJJ.Jd.

j..

to I I _I _I _; i 4

1 I

I l

NEPA Ple*

i

-I s-J l.J.J _l.J _ i_

i l

I_I.I _0!

j a

1 1 I I @i g

g.

l._l _.1_l M 4000 cem si

~ - -' g _'

'J l J _ ki._t l-

~~~

7 i

,,l,

._lJ _t J._,i _i _i g y yy,p iso cem.

6

,- J J J JJ fJ J J J I

g-s. :-._i J

lj J i

i i

s i

-iJJJJJl l

l i (A _.l _.I,.l _.l _J-. I i

i i

i J J _I-l 4

u*ei s g s is g.m.

il i

ll 3

7 I __I I._I l

-i 3

CL1Ari i

i I

, I l d 1

.l l

l lq yI j

d a

7G 0

W 2600 3000 cpm BA O. 4F

~~

s.

FIGURE 13: BUILDING 39 ROOF Z AA BB cc DD EE FF GGHH llJJ KK Lt. MM SURVEYAND LI J _l l

o GRAVEL SAMPLES g _I _I _I _I _I _I _l 4 -b il I

J _I J _i _l _i i i i i

I

~

i JJJJJJ'M t

I

~J[

DJJJJJ_

lj o

y J.; ; _i _ _i _ _u _i _

l_I_Ig _I_l_I_l I

I_l I

}J_l.J_I_I_I_I_I_l._I_4 i_

~

- ~, - -

h = HeatingeCoolingrCondensing Units g

_t J _I J _ f. & I _ I I _ I _t _.

{, e iniot

.; I _l y _ l. _ I I

I i.1 I 4 e

1. ' l

! l J J _t 1 I I _f I

i

.;) J J l

I l-I _1 _I J_ }

O =' Gravel Sample Locations i

iL.1_!1J !_O !J l._1 g

Gravel samples were taken on J. _f. _I t

i I

I I

I i _I _ t.

a five meter triangular grid d h _I _I I

I _I I I l

piaJJ_lJ_i;J.J.a_,

/ J J J l_i_e._I_I_f_I_l fd -l

-lId-b gipsRTURE i

o

_I _i _t I

i i

n+- N CARD 00 cpm BA

$o cpm a 1

8000 cpm py Also AVSIDhI on L

gputuro I

[ _I _.] @ j _I 500 cpm a l

i I

I L

-l - l

~

IJ j _,1 I

l _1 g

Contaminated areas with

,t 3000 to measured radiation levels i

g~g~'

g g

g g

g '5000 Using Pancake GM and P" 8A 50 cm2 alpha hand held I ! 'I I

I.b_ _I :._ I detectors I

I _t _ l,I _lgl_l 100 to 300 cpm a-

' % -j _r',' -l-l -l 0

_i _

i..

%010 J00l7-)

J __I _t__I_.I _I_I,1 JJ_I_I_.I$_I_I

~

J_iiiri l

i i

I I

i g

C i

l Fiaure 14: Roof Tar - Felt Laver Scan l

100% of the tar - felt layer was scanned using 434cm* floor monitors for alpha and beta. gamma.

All areas with elevated readings were surveyed with hand held meters.

l = Contaminated Area, as determined by survey with handheld instruments.

---~----~'

It was removed and disposed of as radioactive waste A

B C

D E

F m-6700sol l

200A i Penthouse 1

2300 2s00 so 2300 - 2400 s o 2300 -2400 s o 1860 -2500 s o 1442 2475 8 0 0 40 0 -40 0 40 0 40 A 0-40A 1400 -1900 s o A

A A

l 0 40 A i

l2 i5 I 2100-2s00so 2000-as7sso l0

O 2400 2s00edY 2

2400 2s00 so 2400 - 2s00 so 0 -40 A 0 - 40 A

,- 4 song 3 49 A 0-40 0 40 A 0

i-- -----,

e g ;i._JMA-l0 l 8000sG l 3 "" _'

l0 l

200A

sG l 2m-24mso l0 t

2m 2m so am-2m so 2m 2m so 2m 2m so em -2m scho 3

0 -40 A 0 40 A 0 40 A 0 40 A 0 40 A 0 40 A l60 iA l

i I 2100 - 2500 l

l i

1900 - 2400 1458 - 2250 sG 1988 2375 s o 2300 - 2400 sG 2300 2400 s o

(

0 - 40 A 0 - 40 A 0 40 A 0 40 A 0 40 A 0 40 A l i

4

,___u_

l #8800 i l

l i isoA i l

i

'~-~-

l 4000-20000so l

l l

50-300A I

2M*2M i

l i

l l

l t

l 5

!38888#8 2100 2500 1900 -2460 s o 1800 2400 BG 1900 - 2400 sG f

0 40 A 0 - 40 A 0 40 A 40 A 0 - 40 A l noA l

4000s o

i i

150A l

I 6

2200 as00 2000 2400 2100 2400 s o 2300 2400 s o 1900 2400 s o l

0 - 40 A 0 40 A 0 - 40 A 0 40 A 0 - 40 A l

l

_ _ _ _ _ - - - ~ 2600 3000BG &Ti4GN ~ ~ - - - -

- - - ~ - - - - ~ ~ ~

- - ~ - - i m

a m

. - M

Figure 15: Roof Tar Felt Layer 100cm2 - 2 Min fixed Measurement Beta / Gamma readings taken every 4 meters A

B C

D E

F MM lrm ll ma I im I j

.4 l l io4. l lnul I n7. l l im l l im l l im l 1

Penthouse lim ll mo I'"l l ins l l im l 1 im l l im l I mi l l uns l I '= l Il us3 I mi l I '=

l im l l ii49 l l 1o27 l l i32,1 l 237. l l isii l I,42. l 1,323 l 2

llim l ni. l lim llim l l im l

[ im l l ms l l mi l j us7 l llimllmr j mi l l im j l im l I,m l l im l lsuil I m. l 1,m l 3

l usi l l 1333 l l 232' l l 1420 l l ises l l i4or l l 240s l l 1387 l l 14ae l lisool i

l 1815 l l im l l "58 l l mo l F'.]

j,,,, j l n44 l l n 3l l-l l uss l l

4 i,m i l,,,, i l== l l im i l im l i

,,,3 i i m. i I,m i i,m l i m i l

1483 5

3 E

L l i= l I nso l l im l I mi j l im i luul l i= l l i= l l im l.

1, E

l v

l 132e l l isos l l i324 l l 1533 l l 135: l l 152: l l uat l i

6 l

\\

l l ms l l mi l l u.i l l"al lim l I mol I ms l l ma l lieel{linal l

l l

p i

~

Figure 16: Roof Tar-Felt Layer Fixed Alpha Measurements 50cm2, 5 - 10 second count alpha readings taken every 4 meters.

)

i r-,rsnn I

A B

C D

E F

l m4a l l a* l l ** l l m4o ! I m o j l na l l m* l l m4o l lmoj l m4a l 4

1 Penthouse I "** l l m4a l l ma j l *** I l>4allm4al l,

l l m4a l lm4allmaj i

l 2440 l l244oll2440l l 204. l l244ll2440l l204ll244ol s

i 2

i f

l *** l l 2040 l l m4o l l 2** l l 868 l lra4ol l 8** I l 8** l l80all2**l 3

I I,,o i I m.o i lml l moi lm.l l-l l m l l,- l lm llm.l l *** l l 2Sa l l m.,

j l roe l l a>= l l,,, l l 2 e l l rae l l eo l l r>

l t -

l 4

ImalImal l ma l IwalImaI l m4. l I me l I ma l I ma l I ma l 1

l 8** l l 8** l l 80# l l 8** l l 8** l lrodol l roe l l roe l l 34o ll l

5

E

<C l m4o l l m4o l l 2*a l l me l l 7 4o l l2540l l Se l l 204o l l

4o ll j

.a i

lm-lIm-l i -- i imai lm-1 i.- i I m-l l - 1 l me I: j l

6

g

.o i

0 244o l l m4o l l 204o l M4o]

l m# l musummusu ummusummer 4

l l

Fiaure 17: Roof Insulation Scan Notes:

l Approximately 50% of the insulation layer was scanned with 434cm' floor monitors. The remaining 50% was broken into small pieces, it was scanned with hand held meters. The broken material was located in the southwest and l

northeast corners.

t B

C D

E F

j ggA M

M l

4040 BG 4640 BG 4040 BG j

i

! 0 40 A 0 - 40 A l 0 - 40 A 1400 1500 BG 1400 1500 BG 1400 1500 BG 0#^

0#^

0-#^

l I

Penthouse I

i l

I I

j l 4040 BG 4040 BG 4040 BG 1400 - 1500 BG 1400 - 1500 BG 1400 -1500 8 0 i

2 0#^

0#^ I O#^

0-#^

0#^

0-#^

l 1400 - 1500 BG l

l 0 - 40 A 5

l I

I I

3 l 4040 BG 4040 BG 1400 - 1500 BG 1400 - 1600 BG 1400 1500 BG 1400 - 1500 BG a. 4o,

o.4o 4 l 0 - 40 A 0 - 40 A 0 40 A 0 - 40 A I

j

__l i

I l

1400 1500 BG 1400 1500 BG 1400 - 1500 BG 4040 BG 46 80 BG 4040 BG l 4

0 - 40 A 0 40 A 0 40 A l

0 40 A 0 - 40 A 0 - 40 A i

i i

I l

l s

i 1400 1500 BG 1400 - 1500 BG 1400 1500 BG l

4040 BG 40-80 BG 40 80 BG 0 - 40 A 0 40 A 0 40 A 0 40 A 0 40 A 0 40 A l

I 16 1M BO im - 1M BG 1m 1M BG

1. 40 BG 4-80 BG

1. 40BG g

l j

0 40 A 0 - 40 A 0 - 40 A 0 40 A 0 40 A 0 - 40 A i

l d

4 1

I l ~ ~ l = areas surveyed with hand held instrm,3ents L. _ J

1 J

Floure 18: Roof Insulation Laver Fixed Aloha Measurements 4

50cm2,5 - 10 second count alpha readings taken every 4 meters.

A B

C D

E F

l mo l l a4o j l *** I I mo l I m4o l I 2$a l 12$a l l 2*a l l **a l 15a l 1

Penthouse l

l *al jaal lmel I "a l I ma l l *a l 12*all*al l

lmolla*l i _.o i i_i i -a i i -a u a i i -a i i-ai i _.o i i_ai i_i l

. l aa l l ~a l l ** J l*al l=al l =a l l ~a l l = l l ~a l l aa l j

3

[ m* l l m4o l I 8**

l l a4o l lmal l ** I lm4ol lmal lmollm4ol l_lImal l aa l l=al I=al I -a l l =a l l =a l

!=all=al l

4 J

l '*a l I al Imal l *a l l=al I=al I ma l 1 4a l i

1.* l l

.o l

]

l m4o l l mdo l l

.o l l m4o l l m4o l l 8*a l l m4ol l m4ol l 2*a l :

5 2

1 i

lmaj l m4o l l,>4o l l m4o l lmal l *** I l m4o l l m4a l l ** I s

\\

l~all~al i mo i I-al leal I mo i l ea l l ea l i,,a i : s 6

h l

15a l l aa l l aa l I ma l l aa l l =a l l =a l l =a l l *a l :

unummumummanusuem muumuseum

j i

i Fiaure 19: Metal Roof Scan Notes: Floor monitor scans on office area metal deck eaualed 0 -41 com aloha 1

and 924 - 1387 com Beta / Gamma. rn = Smear location. 50 smears were l

collected.i rm i = Fixed readings total counts in 2 min.. fixed 100cm2 Beta orobe. 35 fixed Beta counts were taken.

A B

C D

E F

677 733 Si g Penthouse 691 749 5

t i

2

@:g, 706 i

622 T4T l

h A

696 -

l 687 i

l 4

i 653 i

666 l

712 4

721 j

@ 756 3@

i 711 725 681 693 700 692 748 6

(11) 9 b

g]

1

..g...f...g..,..g..,....g.-24--g-m---i 688 682 701 773 685 659 713 722 768 753 741 710 2

399 M

E E

E EMEME E

E j

FIGURE 20: SOIL SAMPLING LOCATIONS FOR OFFICE AREA Legend:

k i

I h= Sample Area I

l B

C D

E F

I i

.I I

Ct,am 8

b s.

1 I

ome.s m w.a F9ga I

Ril an$

I Procese Area 5,.u,-

3

'm los-eWo I

k3;}U$

ngi 4

>aks MM)Yd. -.

ff 4

S.

7"

,:$1 lxmy

@MiT ll g

%3lQ - )

S sd'gggrpg

- p54 g posgj pgw; bs4 aossy ajg e4 gw

,h., r,%w.,e.;,, nsaA e,b a.avw++a,n,.g,,,e,vn w, w an sw wa

i Figure 21: Matrix Room Floor Survey l

North 1

i i

Scan Ranae Data _;

alpha 0 - 50 beta / gamma 1200 - 1400 COntamm.ated i

Area j

Larne Area Smear Data:

i (To be disposed of as radiactive waste)

)

Taken in NW Quadrant 12' 1

alpha = 0-20 cpm j

betalgamma = 4040 cpm Taken in SW Quadrant T

i alpha = 0-20 cpm A

l, beta / gamma = 4040 cpm

/$m\\

-13 uR/hr f

3 uR/hr 4

Taken in NE Quadrant alpha = 0-20 cpm

_.2-.

betalgamma = 4040 cpm

. 13 uR/hr 13 uR/hr l

Taken in SE Quadrant alpha = 0-20 cpm l

b eta / gamma = 4040 cpm T

13 uR/hr 33'3' i

13 uR/br l

Notes:

T 13 UR/hr T

/>A

13 uR/hr 2ox l

b = Fixed Beta 100cm'in epm 2

1-l A = Fixed Alpha T

@ = Smear f

1. = uR/hr reading

~

- r-contaminated 13 uR/hr mM~ : "pa i:

i area 1-

" /- r - concrete to be disposed of as ractuactive waste i

i l

f i

.