Text

Final Radiological Survey Peformed at General Atomics Bldg 31-1
	ML20211H907
Person / Time
Site:	07000734
Issue date:	08/25/1999
From:	Maschka P, Ramirez E, Joseph Turner; GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
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F i

FINAL RADIOLOGICAL SURVEY PERFORMED AT GENERAL ATOMICS' BUILDING 31-1 l

Prepared By:

John Turner, Paul Maschka, Efraim Ramirez, Undree Wells, Steve Finchum, Comelius Stanley, Barbara Lyons, Dane McKay, Joe Sullivan, Scott Cowan, Richard Stowell and Laura Gonzales August 25,1999 E[ $0$0k $$o$I34 C

PDR

Table of Contents INTRO DUCTI ON............................................................. 1

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S ITE DES CRIPTION......................................................... 1 PREVIOUS ACTIVITIES (HISTORY OF USE).................................... 2

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CRITERIA FOR RELEASE TO UNRESTRICTED USE............................ 2 Facilities and Equipment................................................ 2

. Enri ched Urani um.................................................... 2

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Natural Thori um......................................................... 2 Beta Guideline Values (thorium)

...... 3

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Release Criteria for Soils and Roofing Materials............................... '3 Exposure Rate Guideline....................................

...............4 IN STRUM ENTATIO N.....................................................

.4

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BACKGROUND MEASUREMENTS.................................

.... 4 Background Measurements for Instruments / Detectors 4

Background Soil Concentrations............

......... 5

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Background Roofing Material Concentrations....................

.............5 Exposure Rat e Background................................................. 5

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DECONTAMINATION ACTIVITIES

..........................................6 l~

Summary.............................................................6 Classification of Areas.....................................

.............6

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Decontamination................................................

....6 FINAL SURVEYS PE RFORM ED................................................ 7 Objectives and Responsibilities....

7

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S u rvey Pla ns.........................................................8 Sample Preparation and Counting.......................................... 8 Roo fing M aterial Samples.................................................. 8 h

S o il Sampl e s.........................................................8 S URVEY S UM M ARY.......................................................... 9 RESULTS OF THE FINAL SURVEYS........................................

.. 10 S c a n n in g.........................................................

.. 10 Fixed M easurements................................................... 10

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Removable Contamination Surveys......................................... I 1 Exposure Rate Measurements.........................

.....................11 Drains and Drain Lines.................................................. I 1

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Paint Samples..................................

12 Roofing M aterial Samples............................................... 12 p

Roo f S u rveys.................................................. 13 L

S o il Sampl es.....................................................

14 GA INTERNAL CONFIRMATORY SURVEY.................................

.. 14

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S u rvey Plan......................................

...... 14 Results of the Internal GA Confirmatory Survey.........................

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. CONCLUSION..

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11 i.,

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List 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 ofInstroments.........

.. T-3 Table 4:

Background Measurements (Obtained from Building 13)

T-8

)

Table 5:

Results of Characterization Survey................

T-11 Table 6:

Results of Final Surveys in Building 31-1............

. T-12 Table 7:

Results ofIntemal Confirmatory Survey...........

T-15 Table 8:

Results of Final Soil Samples Collected in Building 31-1.

T-16 Table 9A: Results of Tar Samples Collected from the Roof.

T-20

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Table 9B: Results of Gravel Samples Collected from the Roof T-21 Table 9C: Exposure Rate Measurements Taken on the Roof.

. T-22 Table 10: Background Soil Sample Results T-23

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List of Figures (unpaged)

Figure 1:

Plan View of General Atomics Site.

Figure 2:

Building 31-1 in Relation to Surrounding Facilities.

Figure 3:

Diagram of Building 31-1.

Figure 4:

Decontamination Activity Locations.

Figure 5:

Room 103: Exposure Rate Measurements, a/p Scans and Paint Sample Locations.

Figure 6:

Room 103: Fixed Beta Measurements and Removable Contamination Locations.

Figure 7:

Room 104: Exposure Rate Measurements, a/ Scans and Paint Sample Locations.

Figure 8:

Room 104: Fixed Beta Measurements and Removable Contamination Locations.

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Figure 9:

Rooms 101 & 102: Exposure Rate Measurements, n/p Scans and Paint Sample Locations.

Figure 10:

Rooms 101 & 102: Fixed Beta Measurements and Removable Contamination

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Locations.

Figure 11:

Rooms 101 & 102: Overhead Beta Scans & Removable Contamination Locations.

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Figure 12:

Room 105: Exposure Rate Measurements and a/ Scan Locations.

Figure 13:

Room 105: Fixed Beta Measurements and Removable Contamination Locations.

Figure 14:

Room 105: Overhead a/p Scans & Removable Contamination Locations.

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Figure 15:

Room 103/104: Approximate Location of Drains & Drain Lines.

Figure 16:

Room 104 (rest room) & Room 103: Drain / Drain Line Survey. Internal Exposure Rate Measurements and Removable Contamination Locations.

)

Figure 17:

Roof Sample (tar & gravel) Locations.

Figure 18:

Soil Sample Locations.

Figure 19:

RoofSurvey: Exposure Rate Measurements & n/p Scan Locations.

Figure 20:

Roof Survey: Fixed a/p Measurements & Removable Contamination Locations.

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$ c e rat a m es Building 31-1 Final Radiological Survey Report 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 Building 31-1.

This report documents the results of extensive and comprehensive radiological measurements

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completed inside the building, on the roof, and soil samples collected from beneath the concrete floor inside the building and from the footprint area outside the building. The results of these measurements demonstrate that these areas meet the approved criteria for release to unrestricted use.

The building's total surface area to be released to unrestricted use is ~ 1700 f12 (~ 158 m ),

2 Site Description Building 31-1 is located on General Atomics' Torrey Pines Mesa Site. A plan view of the GA Site is shown in Figure 1. The location of Building 31-1 in relation to other facilities at GA's Main Site is shown in Figure 2. A diagram of the building is shown in Figure 3.

The building contains five rooms: rooms 101,102,103,104 and 105. The floors within these rooms are composed of reinforced concrete slabs, except for room 105 which contains both wood and concrete surfaces. The exterior walls of rooms 101,102,103 and 104 are composed of thick cemented, rigid sheets of corrugated fiberboard (transite) which are attached to a structural wood framework and adjoin the edge / footing of the concrete floors. The exterior fiberboard (transite) walls of these rooms are lined on the inside with the wooden framework overlaid with drywall / sheetrock. The interior walls within the building (separating the rooms) are also composed of a wood framework overlaid with drywall / sheetrock.

Room 105 is an annex to the existing building (i.e., rooms 101,102,103 and 104). Room 105 contains 6 storage vault rooms, each surrounded by ~ % foot thick reinforced concrete panels on the sides, bottom and top of each vault, except for the vault doors which are made of heavy gauge steel metal. Outside the vaults, the north (entryway) door and south wall are composed of corrugated metal attached to a wood framework. The west wall of room 105 is actually the exterior (east) wall of rooms 103 and 104 (i.e., rigid sheets of fiberboard). The floor surface in room 105 immediately outside the vault rooms is composed of concrete and the remaining floor surface is made of wood.

Most of the roof consists of heavy duty timber (rafters) which are spanned by wooden decking supporting the roof covering. The wood roof support is overlaid with a layer of gravel and tar. The roof over the vaults in room 105 is composed of concrete overlaid with a layer of tar and gravel.

The remaining portion of the roof over room 105 is composed ofplywood sheets overlaid with a L

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.h cansamm monses Building 31-1 Final Radiological Survev Report 1

layer of tar and gravel.

J Previous Activities (History of Use)

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Building 31-1 contains five rooms: room 101,102,103,104 and 105. Rooms 101,102,103 and 104

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were used as laboratories, offices and as a control room for a critical facility that was previously J

located next door in Building 31-2. Radiochemical operations were conducted in these rooms using Mo-99, Tc-99m and F-18, all of which have half-lives ofless than three days. Room 105 contains

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six concrete and steel storage vaults that were used as an SNM storage area and for storage of source materials, such as thorium.

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Criteria for Release to Unrestricted Use Eacilities and Eauinment 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

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Unrestricted Use," also known as "DECON-1," is shown in Table 2.

The primary contaminates of concern for Building 31-1 are natural thorium and enriched uranium.

l The applicable NRC guidelines for residual surface activity levels involving natural thorium and enriched uranium are provided as follows:

Enriched Uranium The approved guideline values for residual contamination for release to unrestricted use for enriched

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uranium are provided below:

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

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2 2

2 15,000 dpm/100 cm (maximum in a 100 cm area if the average over 1 m is met) 2 1000 dpm/100 cm (removable activity)

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

2 2

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

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

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

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$ cmarmwomes Building 31-1 Final Radiological Survey Report should apply to both alpha and beta measurements, independently, for surface contamination involving natural thorium.'

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

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

2 2

respectively, for beta monitoring.

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

Beta Guideline Values (thorium)

The modified guideline values for residual contamination for release to unrestricted us. Dr natural thorium are provided as follows:

2 2

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

2

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2000 dpm/100 cm p (maximum in a 100 cm area if the average over 1 m is met) l 200 dpm/100 cm p (removable activity) 2 Release Criteria for Soils and Roofine Materials (i.e.. tar & cravel)

The predominant radionuclides found in the soil or within the roofing materials at GA and the release criteria in pCi/g for these radionuclides are provided as follows:

Enriched Uraninm (U-234 + U-235) 30 pCi/g Thorium (Th-228 + Th-232) 10 pCi/g Depleted Uranium 35 pCilg Cs-137 15 pCi/g Co-60 8 pCi/g lf more than one radionuclide exists, the sum of the fractions of the concentrations is calculated as follows:

C, L,

a.n C, = The average concentration of radionuclide iin the sample above background levels.

L, = The release criteria for radionuclide i.

' " Interpretation of Thorium Surface Decontamination Limits," U.S. Nuclear Regulatory Cc,mmission, February 9,1992.

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4 smuusam m macs Building 31-1 Final Radiological Survey Report The sum cf the fractions must be less than or equal to one for the sample to meet the release criteria.

Excosure Rate Guideline l

Exposure rates measured at I m above the surface are not to exceed 10 R/hr above background levels.

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

s (1) a description of the instrument, model number and its serial number, (2) a description of the detector (if applicable) and its serial number, (3) instrument ranges, (4) calibration due dates, (5) typical ba@round readings and (6) calibration efficiencies (if applicable). All of the instruments used were calibrated semiannually aud after repair, except for exposure rate meters which were calibrated quarterly.

Background Measurements Backcround Measurements for Instruments / Detectors

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Building 13 on GA's main site was used for conducting background measurements on instruments used for the final survey because: (1) there is no history involving radioactive materials or storage of 1

radioactive materials in Building 13, and (2) the various surfaces and construction materials found in J

Building 31-1 could also be found in Building 13.

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

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

)

2 Equation (8-II)

_X* q [,, X J

i1 /

n, 1

["(X-X)'

5

/

8]

y_$

Equation (8-12) 1 2 Manual for Conducting Radiological Surveys in Support of License Termination (Draft for Comment),

1 NUREG/CR-5849, ORAU-92/C57, Oak Ridge Associated Universities, June 1992, I

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4 CEMMA& Aronnes Building 31-1 Final Radiological Survey Report 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,x (dpm/100cm ')

MDA =

^

txEx 100 Where:

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

E = efficiency 2

A = area of the detector (cm )

Backcround Soil Concentrations of Concern Typical background concentrations measured by gamma spectroscopy in soil near the GA site have been established (at the 95% confidence level) and are provided in Table 10 with the locations where these samples were taken.

Backcround Roofine Material Concentrations of Concern Typical average background concentrations measured by gamma spectroscopy on samples of roofing materials (tar & gravel) collected from three different locations (5 samples / location) on the GA site, in pCi/g (at

2 6) are shown as follows:

Ig.I Gravel U-238 2.31 pCi/g 4.68 1.35 pCi/g

1.72 U-235 0.27 pCi/g 0.32 0.12 pCi/g 0.14 Thorium (Th-228 + Th-232) 4.84 pCi/g 4.54 2.09 pCi/g 2.82 Cs-137 0.13 pCi/g 0.30 0.33 pCi/g

0.98 Co-60 0.02 pCi/g

0.12 ND (< 0.06 pCi/g)

Exoosure Rate Backcround Typical exposure rate background for this site using a Ludlum Model 19 microR meter is about 15 uR/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 site). Measurements taken offsite in 10 different locations (9 offsite and I onsite at a non-impacted area near Building 15) over a period of15 months also averaged ~ 15 uR/hr (measured at I m from the surface).

The range of M-18 R/hr is typical at the GA site for the external dose rates measured at I meter from the surface. This range increases to 20-23 R/hr for rooms having concrete walls, floors and I

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"' AMSCW Building 31-1 Final Radiological Survey Report ceiling. This background was measured in an all-concrete room in GA's Building 1 (Administrative Office Building). This natural background level increases to 27-30 R/hrin concrete lined trenches and pits, as measured in a concrete pit located near GA's Building 2. The normal background level

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expected in an area surrounded by closely spaced (~5 ft), high density (140 lb/ft ), ~12 inch thick 3

concrete walls, floor and ceiling increases to 30-32 R/hr.

Typical exposure rate background for the specialized, smaller diameter Ludlum Model 44-62 microR detector ranged from 8-12 R/hr measured at I meter from the surface. Typical exposure rate background measured internally within drains and drain lines or pipes ranged from 4-8 R/hr.

Decontamination Activities Summary The locations of the areas within Building 31-1 that were decontaminated are shown in Figure 4.

About 50 ft out of 1700 fl2 floor area (~ 3.0%) was decontaminated. No contamination was found 2

on any of the walls or soil samples collected from underneath and around the building. The tar from the building was found to have elevated thorium / uranium levels; therefore, it was disposed of as radioactive waste. Gravel from the roof was sampled and found to have radiation levels below the l

release criteria. 'No contamination was detected on the wood roof that remained.

Classification of Areas Rooms 101,102,103,104 and 105 and the roof were initially classified as "non-suspect affected" areas. Rooms 101,102 and 105 and the roof were reclassified as " suspect affected" areas after contamination was detected on the floors and in the roof tar.

Non-Suspect Affected Areas: Rooms 103 and 104.

Suspect Afected Areas Rooms 101,102, and 105 and the roof.

)

Decontamination The linoleum tile overlying the concrete floor slabs was surveyed and the levels found to be below the release criteria. The linoleum tile was removed from all of the floors and disposed of as non-radioactive waste.

During scanning surveys in room 101, several small areas of contamination (a and p activity) were detected on the concrete floor. These areas were decontaminated with a concrete scabbler and a jack hammer. The debris was removed and properly disposed of as radioactive waste. Levels decreased to < 121 dpm/100 cm a (measured using a 50 cm a detector) and background levels (100-140 cpm)

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2 2

2 using a 15 cm (GM) pancake detector l

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l* - ='AFORWCW Building 31-1 Final Radiological Suivey Report No contamination was detected in rooms 102,103 and 104.

Several small localized areas of a contamination was detected on the wood portion of the floor in Room 105. These small areas were chipped up, removed and properly disnosed of as radioactive waste. Decontamination was performed on one small localized area of the wooden floor due to elevated levels of a activity discovered during the a scans. This area was surveyed with a hand-held 2

50 cm a detector and the maximum result was equal to 510 dpm/100 cm. This small area on the 2

wooden floor was removed and properly disposed of as radioactive waste.

Exposure rate measurements in the storage vaults were typically 14-17 R/hr except in the southernmost storage vaults (#'s 5 and 6) where the exposure rate was slightly higher (~ 21-26 R/hr). Elevated beta activity levels were also detected using the 434 cm beta floor monitor. These 2

two vaults were decontaminated using a concrete scabbler and then surveyed using a 100 cm p 2

detector. The maximum activity measured was 275 dpm/100cm. The exposure rate measurements 2

decreased to a maximum of 24 R/hr. The two vaults were also surveyed with a 50 cm a detector 2

and the maximum result was < MDA of 121 dpm/100 cm. The resulting debris from the 2

decontamination activity was properly disposed of as radioactive waste. Soil samples were collected from underneath these vaults and the gamma spectroscopy results were found to be at or near background levels.

The roofing material (tar & gravel) was sampled and isotopically analyzed in GA's Health Physics Laboratory. As a results of these analyses, the gravel, which was below the criteria for release to unrestricted use, was removed as non-radioactive waste material and stored for inspection by the NRC and California RHB before disposal to a local landfill. The tar, which was determined to be contaminated above the release criteria, was removed and properly disposed of as radioactive waste material.

Final Surveys Performed Obiectives and Resoonsibilities The objectives of each final survey plan were (1) to demonstrate that the average surface contamination levels for each survey unit were below the approved release criteria,(2) to show that 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 clear removable contamination (i.e., vacuuming & masslinn wipes) and fixed contamination (as necessary), (4) that the exposure rates are less than 10 uR/hr above background measured at 1 meter above the surface and (5) to demonstrate that the soil sample results were below the NRC and State of CA approved release criteria for unrestricted use.

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O cemuram menses Building 31-1 Final Radiological Survey Report J

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

Every survey / sample taken was documented on a daily basis to a worksheet/ drawing showing the approximate locations surveyed / sampled. The documentation included the results of the measurements (including units), the technician's signature, date, instrument (s) used (including the model and serial number of both the ratemeter and detector), calibration due date, % efficiency, background readings (if applicable) and any other peninent information.

Survey Plans Survey plans were developed based on the previous history of the building, the radionuclides of concern, the various types of surfaces, the potential for contamination and the classification of the area (non-suspect affected or suspect affected).

The surveys included a/p scanning of the floors, walls and roof surfaces, collection and analyses (by gross alpha / beta counting) of smears and paint samples, the taking of fixed measurements, exposure rate measurements (uR/hr), and the sampling and isotopic analyses of soil from beneath the concrete within the building and from the footprint surrounding the building and from sampling the tar and gravel on the roof.

The surveys were completed in accordance with approved written Survey Plans.

Samnle Prenaration and Counting Each of the soil and roofing material samples collected were properly logged, labeled, packaged and tracked. Samples were dried, placed into a marinelli beaker (soil samples) or 100 ml plastic containers (tar or gravel), weighed, sealed 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.

Roofing Material Samoles A Roof Sampling Plan was written to sample the tar end gravel from the roof of Building 31-1. All tar and gravel samples were analyzed by gamma spectroscopy in the Health Physics Laboratory.

The isotopic results are provided in Tables 9A and 9B.

Soil Samnles Soil samples were taken from beneath the concrete slab inside the building to demonstrate that the

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soil underneath was not contaminated. This soil sampling along with the final survey taken on top of 8 of 15

f-eh GEREMEA& AFOANCs Building 31-1 Final Radiological Survey Report the concrete slab confirms that the concrete floor slab meets the requirements for release to unrestricted use. The " footprint" surrounding the building (out ~ l meter from the building) was included in the soil sampling survey to ensure that the radioactive materials that were used or stored

)

within the building were totally contained and had not contaminated this area.

f Survey Summary l

The results of the surveys are summarized in their respective tables, as follows: th:: Characterization j

Surveys are summarized in Table 5, the Final Surveys are summarized in Tablo 6 (including the Post Decon Roof Surveys), Internal Confirmatory Surveys are summarized in Table 7, the Soil Sampling Results are summarized in Table 8 and the Roof Sampling (tar & gravel) results are summarized in Tables 9A,9B & 9C.

A summary of the number of fixed measurements, wipes (100 cm ), exposure rate measurements and 2

samples taken during the Characterization, Final and Intemal Confirmatory Surveys are provided as follows:

Building 31-1 Summary of Surveys Performed Survey '

of Fixed

of-

ofExposure Rate

of Samples Taken and Measurements Wipes Measurements Analyzed a

p (100 cm )

( R/hr)

Paint Roof Soil 2

Characterization 33 31 2

Survey Final Sun'eys 19 217 225 186 18 11 tar 43 11 gravel GA Intemal 16 41 20 38

{

Confirmatory Total 35 258 278 255 18 22 45 L

e 9 of 15

p cumsmu mannes Building 31-1 Final Radiological Survey Report Results of the Final Surveys The results for the Final Surveys are provided in Tables 6,8 and 9 and Figures 5 through 20.

Scannine Scans with the 434 cm gas-flow proportional detectors (floor monitors) were conducted in each 2

room for both alpha activity and beta activity in order to identify elevated areas of activity. Areas with elevated readings would then be further investigated with hand-held a and/or beta instruments to determine if the levels were above the release criteria. After decontamination operations and resurveys were completed, no areas were discovered that displayed elevated levels activity. The results of these scans are provided in Table 6 and the locations are shown in their respective figures.

The floor surfaces within rooms 101,102 and 105 (suspect affected areas) were scanned 100% for p and 50% for a with 434 cm detectors and the bottom 2 meters of each wall were scanned 100% for 2

p and 44% for a. The horizontal overhead surfaces in each of these rooms were scanned a minimum of 20% for p.

After the tar and gravel was removed from the roof (suspect affected area), the surface of the roof 2

was scanned 100% with 434 cm detectors for both a and p.

The floors surfaces within rooms 103 and 104 (non-suspect affected areas) were scanned 100% for p and 50% for a with 434 cm detectors and the bottom 2 meters of each wall were scanned 22% for p 2

and 44% for a.

1 Fixed Measurements A total of 10 fixed alpha measurements (1 minute each) were performed during the final surveys in 2

response to the identification of elevated readings discovered during a scans with the 434 cm floor 1

2 3

monitor. The surveys were performed using a 50 cm a hand-held detector.

The applicable background for the 50 cm alpha detector was subtracted from the survey readings

]

2 2

and these readings were converted from cpm to dpm/100 cm using the appropriate count time, the efficiency of the detector and the geometry of the detector. The maximum fixed a result was 324 q

dpm/100cm. The re:ults are provided in Table 6 and the approximate locations are shown in their j

2 respectiw figures.

A total of 217 fixed beta measurements (2 minutes each) were performed during the final surveys 2

(i.e., floors, walls and roof). These measurements were taken using a 100 cm gas-flow proportional

)

detector.

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4 ca mara m annes Building 31-1 Final Radiological Survey Report The applicable background for the 100 cm beta detector was subtracted from the survey readings 2

and these readings were converted from cpm to dpm/100 cm using the appropriate count time, the 2

efficiency of the detector and the geometry of the detector. The maximum fired p measurement 2

result was 554 dpm/100 cm The results are provided in Table 6 and the approximate locations are shown in their respective figures.

Removable Contamination Surveys 2

A total of 225 wipes (100 cm ) were taken during the final surveys. Removable contamination measurements (wipes) were performed on all surfaces including the floors, walls, roof and some inside overhead stmetures.

The wipes consisted of using a Whatman Filter Paper (4.7 cm diameter) and wiping an area of ~

2 2

100 cm. The wipes were counted in GA's Health Physics Laboratory using a Canberra 2400 low level alpha / beta counting system. The wipe results in dpm/100 cm for both alpha and beta are 2

provided in Table 6 and the approximate locations are shown in their respective figures. The maximum wipe results were 51 dpm/100 cm a and 10 dpm/100 cm p, 2

2 f

Exposure Rate Measurements A total of 186 direct radiation exposure rate measurements were taken at a minimum of I every 4 m z inside the building and on the roof. The measurements were taken at contact or at ~1 meter above j

the surface using a microR meter. The exposure rate measurements are provided in Tables 6 & 9C and areas surveyed are shown in their respective figures.

Exposure rate measurements conducted inside the facility in rooms 103 & 104 (non-suspect affected areas) ranged from 14 to 17 R/hr. Measurements inside the facility in rooms 101 and 102 (suspect affected areas) ranged from 15 to 17 R/hr. Measurements on the suspect affected roof area before the tar and gravel was removed ranged from 12 to 14 R/hr. Measurements on the suspect affected roof area after the tar and gravel was removed ranged from 13 to 16 pR/hr.

Exposure rate measurements taken outside the vaults in room 105 (suspect affected area) ranged from 13 to 17 R/hr. Measurements taken inside the vaults in room 105 (suspect affected area) within vault #'s 1 through 4 ranged from 14 to 15 R/hr and ranged from 19 to 24 uR/hr within vault

's 5 and 6.

Drains and Drain Lines Surveys were conducted on the exterior surfaces of the drains and drain lines located in room 103 2

2 and room 104 (restroom) using a 15 cm GM pancake detector, a 50 cm a detector and a Ludlum Model 19 microR meter ( R/hr). All a/p readings were less than or equal to typical background levels. The exposure rate measurements were all equal to 14 R/hr at ~1 meter above the surface.

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.l+crusnataronnes Building 31-1 Final Radiological Survey Report

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The survey results are provided in Table 6 and the approximate locations are shown in Figures 15 and 16.

After the external surveys were completed, the drain lines were disassembled into easily accessed portions for conducting the interior surface surveys. A total of 7 wipes (100 cm ) were taken from 2

within the drains and drain lines. The maximum activity from the 100 cm wipes was < 10 dpm/100 2

2 cm for both a and p. Exposure rate measurements of the interior surfaces were taken using a Ludlum Model 3 Meter with a 44-62 microR detector (specialized detector used to survey inside the drain lines). Interior exposure rate measurements ranged from 3 to 6 R/hr. The survey results are provided in Table 6 and the approximate locations are shown in Figures 15 & 16.

Samples of the residue deposited within the drain lines were obtained whenever available and/or accessible. Isotopic analyses identified thorium as the only radionuclide present in these scrapings.

Using the Canberra 2400 I.ow Level a/p counter in the HP laboratory, the activity present in the

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scrapings was s 3.0 pCi/g, which is below the release criteria for thorium.

1 Paint Samnles A total of 18 paint samples were obtained from the walls in rooms 101,102,103 and 104. The paint samples were counted in GA's Health Physics Laboratory using a Canberra 2400 low level alpha / beta counting system. The results are provided in Table 6 and approximate locations are shown in their respective figures. The maximum results were < 10 dpm/100 cm a and 87 dpm/100 2

2 cm p.

At each location where a paint sample was collected, a 2 minute fixed p measurement was taken 2

with a 100 cm detector before and after the paint removal. The maximum fixed p measurement 2

2 result was 230 dpm/100 cm before the paint was removed and 373 dpm/100 cm after the paint was removed. The results are provided in Table 6 and the approximate locations are shown in their respective figures.

RooGnp Material Samoles A total of 22 samples were collected from the roof, eleven samples were taken of the gravel and eleven samples were taken of the tar at - every 4 meters. Each sample was analyzed separately by gamma spectroscopy. The locations are shown in Figure 17 and the results are provided in Tables 9A and 9B.

The results of the analyses from the 11 gravel samples showed all of the samples, after background concentrations were subtracted, were below the release criteria for each radionuclide of concern.

The gravel was removed as non-radioactive waste and stored pending approval from the State RilB or NRC to dispose of this material to a local landfill.

12 of 15

4 m usuemsmronnes Building 31-1 Final Radiological Survey Report The results of the analyses from the 11 tar samples collected from beneath the gravel showed that the radionuclide concentrations exceeded the release criteria (after background concentrations were subtracted) for thorium (Th-228 + Th-232) and enriched uranium (U-234 + U-235). The tar was removed and properly disposed of as radioactive waste.

At each of the 11 sampling locations, exposure rate measurements ( R/hr) were taken on contact and at I meter above the sampling location. The maximum exposure rate measurement was 14 R/hr.

Also, at each of the 11 sampling locations, the surface was scanned using a 15 cm GM pancake 2

2 detector and a 50 cm a detector. The readings with the GM pancake detector were all less than or equal to typical background levels and the maximum reading using the 50 cm a detector was 139 2

2 dpm/100cm. The locations are shown in Figure 17 and the results are provided in Table 9C.

Roof Surveys After the tar and gravel were removed from the roof, the surface of the roof was surveyed. The entire roof area is overlaid with wood, except for a portion over the vaults which is composed of concrete. The results of these surveys are provided in Table 6 and approximate locations are shown in Figures 19 and 20.

One hundred percent (100%) of the roof surface was scanned for both alpha and beta using 434 cm 2

}

gas-flow proportional detectors. No areas were discovered that displayed elevated levels of a or p l

activity.

A total of 9 two minute fixed beta measurements were taken using a 100 cm gas-flow proportional 2

detector. The maximum fixed p result was < MDA of 184 dpm/100 cm for wood and < MDA of 2

2 212 dpm/100 cm for concrete.

A total of 9 fixed alpha measurements were taken using a 50 cm a detector. The maximum fixed a 2

2 result was 139 dpm/100 cm,

2 2

A total of 25 wipes (100 cm ) were taken. The maximum wipe result was < 10 dpm/100 cm for both alpha and beta.

A total of 40 exposure rate measurements were taken at ~ 1 meter above the surface of the roof using a microR meter. The results ranged from 13 to 16 R/hr. A total of 10 exposure rate measurements were also taken at contact with the surface of the roof using a microR meter. The exposure rates taken were evenly spaced across the roof and the results ranged from 14 to 17 R/hr.

t I

I 13 of l5 1

O N "8"N Building 31-1 Final Radiological Survey Report h

l Soil Samnies J

A total of 45 soil samples were collected from beneath the concrete inside the building and from the outside footprint (~ l meter out) surrounding the building. There were 31 soil samples taken from beneath the concrete within the building and 14 from the footprint sutrounding the building. Gamma spectroscopy results are provided for these samples in Table 8 and the sample locations are shown in Figure 18. Background soil sample results are summarized in Table 10. The isotopic results of every sample showed levels were well below the release criteria.

GA Internal Confirmatory Survey Survey Plan GA conducted an Internal Confirmatory Survey to ensure that results of the Final Survey are indeed below the State of California RHB and NRC release criteria. This survey was conducted in accordance with a written survey plan, by IIealth Physics Technicians not assigned to perform the Final Survey (i.e., an independent survey). The plan required the following surveys:

GA Internal Confirmatory Survey Type of Survey Suspect Affected Area Suspect Affected Area Non-Suspect Affected Rooms 101 & 102 Room 105 Area Rooms 103 & 104 Concrete Floor Scans 25% p 25 %

10% p 2

using 434 cm probe Concrete Floor 4 readings in each room I reading in each vault 2 readings in each room Fixed Measurements p only 3 outside vault p only 2

(2 min.) using 100 cm p only probe Lower Wall Sean 10% p only, along bottom 10% p only, along bottom None Required 2

using 434 cm probe 14"(one probe width) 14"(one probe width)

Removable 4 on the floor of each I in each vault 2 on the floor of each Contamination Wipes room 2 outside vaults room MicroR Readings scan - take 4 readings scan - take 1 reading scan - take 4 readings

@1m in each roorn in each vault in each room above surface 3 outside vaults The results of the Intemal Confirmatory Survey are provided in Table 7 and a summary is provided as follows:

14 of15 1

h SENWurA& AFWAWCW Building 31-1 Final Radiological Survey Report

.Results of the Internal GA Confirmatory Survey A total of 12 two minute fixed measurements were taken in rooms 101,102,103 and 104. The maximurn result was 327 dpm/100cm,

2 A total of 9 two minute fixed p measurements were taken in room 105. During fixed p measurements taken inside the two southernmost vaults (# 5 & 6) elevated readings were found. The floors of these two vaults were decontaminated with a concrete scabbler. A total of 20 (2 minute) fixed p measurements were then taken in vault #'s 5 & 6 after the decontamination was completed.

The maximum result was 275 dpm/100cm,

2 2

Scans with a 434 cm beta gas-flow proportional detector (floor monitor) were conducted on the floors in the non-suspect affected areas and on the flocrs and walls in suspect affected areas. After decontamination was completed, no areas were discovered that displayed elevated levels of p activity.

A total of(16) fixed a measurements were also taken in vault #'s 5 & 6 after the decontamination was completed and the maximum results was < MDA of 121 dpm/100 cm,

2 2

A total of 20 wipes (100 cm ) were collected. The maximum results were < 10 dpm/100cm for a 2

2 2

and 24 dpm/100cm for p, well below the release criteria of 200 dpm/100cm,

A total of 38 exposure rate measurements were taken. Exposure rate measurements ranged from 15 to 17 R/hr in rooms 101,102,103 and 104. In room 105, after the decontamination in vault #'s 5

& 6 was completed, the exposure rate measurements ranged from 14 to 23 R/hr at 1 meter above the surface. Higher exposure rate measurements in vaults are not unusual because of the concrete construction materials and relatively closely spaced walls.

Conclusion Final contamination and radiation surveys, as well as soil sample results, provided in this report for Building 31-1 demonstrate that the building and the soil underneath the building and in the surrounding footprint meet the approved criteria for release to unrestricted use.

15 of15 1

Table 1: USNRC'S ACCEPTABLE SURFACE CONTAMINATION LEVELS l

Nuclides*

Average ##

Maximum "

Removablebed 6

6

)

(dpm/100cm )

(dpm/100 cm')

(dpm/100cm )

2 2

U-nat,235U,238U, & associated decay products 5,000 a 15,000 a 1,000 a Transuranics,226Ra, 22sRa, 23 Th, 22sTh, 23'Pa, 100 300 20 2nAc,1251,1291 Th-nat, 232Th, "S r, 223Ra, 224Ra, 232U, i26j, i33,

1,000 3,000 200 I

13:g Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except "Sr and other noted above.

Where surface contamination by both alpha-and beta / gamma-emitting nuclides exists, the limits a

established for alpha-and beta / gamma-cmitting 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 and geometric factors associated with the instmmentation.

Measurements of average contaminant should not be averaged over more than 1 square meter.

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

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

2 The amount of removable radioactive material per 100 cm of surface area should be determined 2

e by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects ofless surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.

f The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad /hr at I cm and 1.0 mrad /hr at I cm,

2 2

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

T-1

Table 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS Nuclides' Average '

Maximurn.d,r Removable.e,r b

b b

2 2

2 (dpm/100cm )

(dpm/100cm )

U-nat, 235U,238U, & associated decay products 5,000 15,000 1,000 Transuranics,226Ra,228Ra, 23 Th, 228Th, 23 'Pa, 100 300 20 227Ac, 25( i291 Th-nat, 232Th, "Sr, 223Ra, 224Ra,232U, 26i,133,

1,000 3,000 200 I

i3i Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except "Sr and other noted above Where surface contamination by both alpha-and beta / gamma-emitting nuclides exists, the limits estabhshed for a

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 and geometric factors associated with the instrumentation.

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

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

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

The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that

~

2 e

area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects ofless surface area is determined, then pertinent levels should be reduced proponionally and the entire surface should be wiped.

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

2 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.

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

T-2

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Tcble 4: Bcckgrcund Mensurements (Obtained from Building 13)

Ludlum Model 2221 Ratemeter s/n 84734 with Model 43-37 Probe s/n 086236 2

Alpha Floor Monitor Backgroiund Scan Results: 434 cm Detector (Efficiency = 21.15%)

Background Material Alpha Scan Range (cpm)

Concrete 4-24

/

Linoleum over Concrete 0-15

)

Wood 0-21 Ludlum Model 2221 Ratemeter s/n 97287 with Model 43-37 Probe s/n 086238 2

Alpha Floor Monitor Backgrolund Scan Results: 434 cm Detector (Efficiency = 21.90%)

Background Material Alpha Scan Range (cpm)

Concrete 0-20 Drywall / Sheetrock 0-15 Metal 0-20 Wood 0-15 Ludlum Model 2221 Ratemeter s/n 84459 with Model 43-37 Probe s/n 086213 2

Beta Floor Monitor Background Scan Results: 434 cm Detector (Efficiency = 21.85%)

Background Material Beta / Gamma Scan Range (cpm)

Concrete 1858-2036 Drywall / Sheetrock 770-937 Metal 816-1047 NVood 1061-1262 Linoleum over Concrete 1188-1462 Ludlum Model 2221 Ratemeter s/n 86302 with Model 43-37 Probe s/n 086215 2

Beta Floor Monitor Background Scan Results: 434 cm Detector (Efficiency = 22.84%)

Background Material Beta / Gamma Scan Range (cpm)

Concrete 1276-1530 Metal 853-1185 Wood 915-1244 Linoleum over Concrete 867-1134 i

T-8

I Table 4: Background Measurements (Obtained from Building 13)

Ludlum Model 2221 Ratemeter s/n 86332 with Model 43-68 Probe s/n 142540 2

100 cm Beta Detector (Efficiency =28.80% )

Background Material Average of10 Measurements MDA 2 minutes each (cp2m

20)

(dpm/100 cm )

2 Concrete 1059*74 267 Drywall / Sheetrock 581

38 199 Metal 550

52 194 Wood 636

52 208 Ludlum Model 2221 Ratemeter s/n 84423 with Model 43-68 Probe s/n 119444 2

100 cm Beta Detector (Efficiency =35.50% )

Background Material Average of10 Measurements MDA 2 minutes each (cp2m

20)

(dpm/100 cm )

2 Concre'.e 1011

48 212 Drywall / Sheetrock 542 62 156 Metal 655 70 17) f Wood 757

92 184 Ludlum Model 2221 Ratemeter s/n 148436 with Model 43-68 Probe s/n'120477 2

100 cm Beta Detector (Efficiency =27.06% )

Background Material Average of 10 Measurements MDA 2 minutes each (cp2m 20)

(dpm/100 cm )

2 Concrete 933

38 268 Drywall / Sheetrock 510

30 199 Metal 575

28 213 Wood 719

60 236 Ludlum Model 3 s/n 138880 with Model 44-9 Probe s/n 145963 2

15 cm Beta / Gamma Detector (Efficiency = 22.05%)

Background Material Beta / Gamma Scan Range (cpm)

Concrete 100-140 Drywall / Sheetrock 60-100 Metal 80-100 Wood 80-120 T-9

j Tcble 4: B:ckground Me:surements (Obtcined fr:m Building 13)

Ludlum Model 3 s/n 143349 with Model 44-9 Probe s/n 145967 2

15 cm Beta / Gamma Detector (Efficiency = 21.25%)

Background Material Beta / Gamma Scan Range (cpm)

Concrete 80-120 i

Drywall / Sheetrock 40-100 Metal 80-120 Wood 60-120 t

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{

Table 5: Results of Characterization Surveys in Building 31-1 f}

Maximum Scan Results Scan Results

of Results Exposure Location 434 cm p 434 cm a Wipes (dpm/100 cm )

Rate Range 2

2 2

(cpm range)

. (epm range)

(100 cm )

W) 2 a

p

@ l meter Non-Suspect Affected Areas Large area masslinn surveys were conducted on all of the linoleum tiled floors and the activity was measured on the cloths with a hand-held 15 cm GM pancake detector. All readings were s to typical background levels of 60-120 cpm.

2 Room 103 - Floor 900-1600 1-28 6

< 10

< 10 15 Room 103-Walls 910-1500 1

< 10

< 10 Room 104 - Floor 900-1600 1-28 4

< 10

< 10 14-15 Room 104 - Walls 910-1500 4

< 10

< 10 Suspect Affected Areas (Reclassified)

Large area masshnn surveys were conducted on all of the linoleum tiled floors and the activity was measured on the cloths with a hand-held 15 cm GM pancake detector. All readings were s to typical background levels of 60-120 cpm.

2 Rooms 101 & 102 - Floor 900-1600 1-28 5

< 10

< 10 15-16 Rooms 101 & 102 - Walls 910-1500 5

< 10

< 10 900-1600 1-152 2

< 10

< 10 15-16 id v

Two measurements on the wooden portion of the floor (surveyed with a 434 a em probe) showed elevated readings of 62 2

cpm and 152 epm a activity. These two elevated areas were scanned with a 50 cm a detector and all readings were less 2

than 40 cpm (< 324 dpm/100cm ). A portion of the wood was removed and sent to the IIP laboratory where it was gamma 2

scanned. Isotopic analyses showed thorium gamma specs at or near background levels.

Room 105 - Walls 910-1500 Ro 1200-2600 1-28 6

< 10

< 10 15 24 d -

)

The readings on the concrete floors within vault #'s 5 & 6 (southernmost vaults) that were scanned with a 434 cm p 2

detector ranged from 1200-2600 cpm. The readings on the concrete floors within the other four storage vaults ranged from 1250 epm to 1640 cpm. The floors within vault #'s 5 & 6 were decontaminated and resurveyed during & after subsequent surveys.

Room 105 - Walls 910-1500 (inside vaults)

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Table 9C: Exposure Rate Measurements (pR/hr) taken on the Roof of Building 31-1

,2,3 i

i Sample ID (Location) on the surface at 1 m 31-1-1 12 12 31-1-2 U

12 31-1-3 13 13 31-1-4 12 12 j

31-1-5 13 13 31-1-6 13 13 31-1-7 13 13 31-1-8 13 13 31-1-9 13 13 31-1-10 14 14 31-1-11 14 14 Average 13 13

(

' Measurements were taken at each sampling location.

2 Sample locations are provided in Figure 17.

3 Before sampling, each of the 11 sampling locations were also scanned using a 15 cm GM 2

pancake detector and a 50 cm a detector. The readings with the GM pancake detector were all 2

s to typical background levels of 80-120 cpm. The maximum reading with the 50 cm a detector 2

2 was 139 dpm/100 cm,

T-22

Table 10: Background Soil Sample Results '

Radionuclide Concentrations (pCi/g)

Sample Th-228 Ra-228 Total Cs-137 U-238 U-235 jl-) 2 Average of (Th-232)

Thorium 238/583 kev Average of Th-228 +

661 key 92.77 kev peak 186 (144) kev peaks 338/911 kev peaks Th-232 peak Peak AJ 1.28 i 0.07 1.47

0.14 2.75 ND 1.98 i 0.31 0.15 0.03 G2 0.92

0.07 1.01

0.12 1.93

0. I 2 0.03 1.86

0.29

0. I 2 0.02 AC 1.29 0.07 1.34 0.14 2.63 ND 2.27

0.27 0.20 0.03 BKG-1 1.40

0.16 1.44 0.28 2.84 ND 2.06 0.48 0.19 0.06 BKG-2 1.54

0.15 1.57 0.27 3.11 ND 2.30 i 0.45 0.17 i 0.05 BKG-3 1.40 0.14 1.62 0.26 3.02 ND ND 0.19 0.05 BKG4 0.67

0.09 0.84

0.I7 1.51 ND 1.15

0.37 0.09 0.04 BKG-5 1.51

0.16 1.79 0.31 3.30 ND 2.77 i 0.67 0.12 i 0.06 BKG-6 0.68 0.09 0.76 0.16 1.44 ND ND 0.08 0.03 BKG-7 1.17 0.12 1.28

0.22 2.45 ND 1.83 0.43

0. I 1 0.04 Mean

2 o 1.19 0.64 1.31

0.68 2.5 1.32 2.03 0.93 0.14 *0.09 Samples ganuna scanned for I hour.

ND = < 0.1 pCi/g for Cs-137, < l.0 pCi/g for U-238 2

Samples collected in June and August 1993, typically about 1-2 miles from the Building 37 site at the following locations:

AJ Collected on a hillside west of Buildmg 39 & northwest of buildmg 37, ~3' from G A's fence.

G2 Collected about 1200 feet west of Bldg I (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 Buildmg 37.

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

DKG-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.

DKG-6 Collected about 2 miles northwest of Buildmg 37 on North Torrey Pmes Road BKG-7 Collected about 2 miles near V.A. Hospital on La Jolla Village Drive (southwest)

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1 P N

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~ = 2 meters Notes:

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2. Alpha and Beta Scans were completed within the cross hatched area.

3. Exposure Rate Measurements were taken every 2 meters and results ranged from 14-16 R/hr.

4. h = Approximate location of Paint Sample.

J

i Figure 6: Room 103. Fixed Beta Measurements and Removable Contamination Locations.

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2. O = Approximate location of 2 minute Fixed Beta Measurement.

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2

Figure 7: Room 104. Exposure Rate Measurements, alp Scans & Paint Sample Locations.

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Q = Approximate location of Paint Sample.

4.

3

Figure 8: Room 104. Fixed Beta Me :urements & Removable Contamination Locations.

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ROOM 104

\\

0 s""ctum 1 g a

g a

g e

U Floor

.i N

O O

F

/

O 40 0

O O

O o

l O

O O

s Walls O @

O O

i Walls M 2 meters 0

i O

g O

Structure 1 O

Q O

Structure 2 i

Notes:

1. Survey results are provided in Table 6.

2. C = Approximate location of 2 minute Fixed Beta Measurement.

3. @ = Approximate location of wipe (100 cm2),

l I

Figure 9: Room 101 & 102. Exposure Rate Measurements, alp Scans & Paint Sample Locations.

10 9

8 7

6 5

4 3

2 1

1 V A

g Walls B

.i C

I ROOM 102 s

D Door

.g F

G 4

H Floor 1

ROOM 101 K

r I

L Walls M

\\

Door M = 2 meters Notes:

1. Survey results are provided in Tables 5,6 & 7.

l

2. Alpha and Beta scans were conducted within the crossed hatched area.

3. Exposure Rate Measurements were taken every 2 meters and results ranged from 15 to 17 pR/hr.

h = Approximate location of Paint Sample.

4.

Figure 10: Room 101 & 102. Fixed Beta M:asurements & Removable Contamination Location?

10 9

8 7

6 5

4 3

2 1

bUbU bU Walls

^

w oeo@o@

S Do

@o@

o@o

@o c

ROOM 102 i

o@ o@o@o@

o@

o

@o @o@o@o

@o e

o @, o @ o@o@

o@

F

Doo,

@o @o@o@o

@o a

f o@

o @ 0 8 o @. 0@

N Floor

@o

@o@o@o

@o i

o@ o@08o@

O@

J ROOM 101 8o

@o@o@o

@o k

f C@o@

o@

Walls

- @o@o@o l

M Door

_M = 2 meters Notes:

1. Survey results are provided in Table 6.

2. [ = Approximate location of 2 minute Fixed Beta Reading.

3. @ = Approximate location of wipe (100 cm ),

2

Figure 11: Room 101 & 102. Overhead Beta Scans & Removable Contamination Locations.

10 9

8 7

6 5

4 3

2 1

/

1 r g_

vent %

A w,,,,

g B

ROOM 102 17 c

Ceiling 18

\\.

16 D

(15

~

e Fire Spnnkler System

~

F (1[4) f Ceinne yb (6)M cm

<ea s

10

~

v 1

ROOM 101 Light y

Fixtures l

,m Ceiling l

( 4,4 g

J Q

@ [l

( 2E

[

l h

L I

M

_h' = 2 meters i

Notes:

1. Survey results are provided in Table 6.

2. Approximately 20% of the horizontal overhead structures were scanned for beta (i.e., lights, pipes, vent through wall) and all results were less than or equal to typical background levels.

h = Approximate locations of wipe (100 cm ),

3.

2 I

Figure 12: R cm 105. Exp: cure R te M2ccurem:nts & a./p Sctn Lcc:ti::n2.

'e Metal Wall

. e-Ni e.

Concrete Vault x

,.i C

/ oncrete Floor Walls

/F Wood f

f Floor

-y' 6

'e

/

.i e:

l e-e 5

e:

e l

e:

e 4

.e l

e e

3

/s dutside' surface'

,of rnetal door,

I e.

' l'nside surface e

2 r of metaldoor e

e l

'e.

i 1

^'

/

Concrete Vault Fiberboard Floors (Transite) Wall Concrete Vault

-P.

p Wall Wood Framed Metal Doors flo!9E

1. Survey results are provided in Tables 5,6 & 7.

2. Alpha and Beta Scans were completed within the cross hatched areas. Scans were also taken on the side wall within each vault.

3. Exposure Rate Measurements were taken every 2 meters and results ranged from 14 to 24 pR/hr.

Figure 13: Room 105. Fixed Beta Measurements & Removable Contamination Locations.

Metal outside Door h Wall

/

\\

D" f@

i

\\f 0

U Od O

29 8@l N

0 0

s o' f@0 ROOM 105

/g g f

@ o o

25 15 Fiberboard f

(transite) Wall

@ 0 N

O outsid Door Concrete

/

Wall Inside Door OmA

'@ o !

i 0

0' /@

o e

19 @l s

0 0-A+

/

i s

/

\\

l

/

A 0\\

~

Concrete

/\\

i Wood Floor

'\\

,j Floor d

J Notes:

1. Survey results are provided in Table 6.

l

2. e =

,_,_1e,_e_,.,,..

, o.

.,_,_,e,_,,_,2 _e med een--t te-ine ri-m

Figure 14: Room 105. Overhead alp Scans & Removable Contamination Locations. I l

J All scans taken on 31 '

1 P 6

ceiling g

(within vaults)

N-

. f l

h M.

y

'.h-f 5

9 G

4 f\\

Shelves Vaults Light Fixtures

..h.-

f

)

3 p

e :

l 2

/

All wipes taken on ceiling (within vaults)

N 1

l I

Notes:

1. Survey results are provided in Table 6.

h = Approximate location of wipe (100 cm2).

2.

3. Within the cross hatched area,100% of the ceilings were scanned for alpha & beta with a 434 cm detect 2

Figura 15: Room 103/104. Approximate Location of Drains & Drain Lines.

1 r N

1 8

7 6

5 4

3 0

Drain Line w/ cap (B)

Room 103 4

Drain Line (C)

,.,,,, M l

U

(

C 69 Drain Line (A)

D

\\@

Room 104 F

Door\\

= 2 meters r

Notes:

q

1. Survey results are provided in Table 6.

2. Drain lines (B) and (C) are located within the wall space bety een i.. oms 103 and 104.

3. Drain line (C) was not dismantled as it services the toilet in room 104.

4. h = Approximate location of drains and drain lines.

Figure 16: Room 104 (rest room) & Room 103. Drrin/Drcin Lins Surv:y.

Intern:l Expr ura R:te Me:Curem:nts cnd R::m v bis Centamin:ti:n Lec tinn3.

[d 4

N Room 104 l

d Rest Room (A)

~,

n S

y

[ 5 pR/hr Vent

&sjs N-

/

W Section Removed l g:ggjgg:gg;gg j p ~@

Room 103

/

$u D.......g. % [' &.

y aH

?

Concrete Floor Sewer Line n

(B) venti b Room 104

$g g@i; Rest Room fj Lavatory c,

Yh 6 R/hr Section Removed j

(

w v,:

e, a

y..

N-J W all

.M 5 R/hr

~G l

j

.., y IkY N

N P3 3 pR/hr

[

)

U Section Removed l

h]

~

Notes:

6 R/hr q #

1. All drain pipes are made of metal.

\\'

\\

i

2. h = Approximate location of wipe (100 cm ).

2 5 R/hr

3. Results are provided in Table 6.

4 Figure 17: Roof Sample (tar & gravel) Locations.

1 r N

~2m

~2m-

~*

ROOF

\\

l a

h

~2m

~3m O

G l

/

//

m

1. Sample results are provided in Table 9.

h = Approximate location of Roof (tar & gravel) Sample.

2.

t

ll11 jil l!

l 14 o

Q 0

7 3N 1

1

=<

=

8 m

m gm m

$^

3 5

q 2

2 1

+

0 7

4 1

1 2

1 m

1 5

7 1

2 1

0 0

1 1

4 m

g m

m o

o 9+

i 8

o 5

o 1

R 2

i R

1 1

2 1

1 m

5 1

4 0@>

\\

1 2

9 6

3 I\\j 2

1 1

1 m

5 1

-4 2

l 1

@tT

+

6 m

m m

5 5

5

)

. m 1

1 1

e 4

lp 8

5 m

4 m

4 4

0 4

e a

1

{ 5.1 @

m l

S m

m b

J5

$a m

a i

2 1

1 o

T il 1

o R

in S =

o f

d o

e 3

d no m

0 m

3 iv it 3

1 3

1 o.

a m

p c

o e

lo r

e o

a ta R

s m

ltu ix s

o 2

e r

m 7

t r

p e

p s

M

. O-o 5

eRo lp A

R m

=

a S

l io S

s 1

2 e

to s

n n

m o

i 5

-4 0

h.

ita a

m 1

4@

mb c

m 7

2 1

o 4

o 2

2 hA L

o l,

)j

=/

R j

/

e lp 2

i m

s.

_ 6 l

4 O

~

}

a s.

1 S

g io g

l

[

9 8

6 5

3 S

3 2

2 2

8 1

eru g

1 g

iF fil l

i Figure 19: Roof Survey. Exposure Rate Measurements & alp Scan Locations.

~ 13 m N

7 6

5 4

3 2

1 r.

I f.

/

f.

/

f.

/

~

j /

/

'/

/

Wxd

/

O Concrete.

Y

/

\\i

&./

/

./

/

./

/

./

/

. /.

. /..

./.

. /..

..y..

./.

. /..

./.

}

/,

~

/

fl

/

fi

/

fi

/

/.h,lY #

/

l

/

./

/

./

/

/

/

p V

/.

/

/ Roop.s

/

c

,)-

Y

/%

/:

/

/:

/

/ :'

f

/

~ 10 m ri

/

if

./

/

J /'/

/ ' /

T,h,.. :./ g /

/

.y./

... /... ; y.,.

i i/

/

i/

/

. y..

',. /g /.,

. y,.

y

..y,.

..y.

./.

d

/

/~

/

lD

}/

,/./

/

~7m l

/

).

l/

/

?

/

B l*

ll

/

f'/

/

/ ~

/

./

/

e

./

/

./

/

l!..),..l,,..., ft

..) 7.,/.

- (..

./.

. 7..

. /..

.f.

./.

g]

/

/l

/

,/

/

(p 7

/

,/

/

A

~ 17 m ME = 3 meters Notes:

1. Survey results are provided in Table 6.

2. Surveys were conducted after the tar & gravel were removed from the roof.

3. Within the cross hatched area,100 % of the roof surface was scanned for alpha and beta using a 434 cm detector.

2

4. Exposure Rate Measurements were taken every 2 meters @ ~ 1 meter from the surface and results ranged from 13 to 16 pR/hr. Exposure Rate Measurements were also taken at contact with the surface and results ranged from 14-17 R/hr.

9

)

Figure 20: Roof Survey. Fixed alp Measurements & Removable Contamination Locations. i i

N 7

6 5

4 3

2 1

i.

x Wood gfy D

P D

a Concrete.

1

.r a

Es Nx,e.

366p 4

+i 9"@!

is D

s c

z a

ac G

.a..

e s

e p

e E

s s @

B 9

g:

,i gj e

.=p

f@* @ hl p

@a p @

@a A

"&,. y

9 p e m m 4 *

v @k @ w + %, m. m--, /

,e, 3. n, e u

L

]l W ;[llh h};.j_f-l p, n g s ; A g g ; y; n 4m e

l'jfk$({f"Ugg;gs,,,:-r: R {, g --

pyy:r q

w. :cph ; cyp, mMg.5Fh jfy:

i?i$rg f f Y,.

p:

M' = 3 meters Notes:

1. Survey aesults are provided in Table 6.

2. Surveys were conducted after the tar & gravel was removed from the roof.

3.

= Approximate location of 2 minute Fixed Beta Measurement.

4.

ot

= Approximate location of Fixed Alpha Measurement.

5. Q = Approximate location of wipe (100 cm ),

2

-

ML20211H907

Text

*2 gg pa

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