ML20196H558

Final Radiological Survey Performed at General Atomics Bldg 35-1

ML20196H558
Person / Time
Site:	07000734
Issue date:	03/05/1999
From:	Gonzales L, Maschka P, Ramirez E GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
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ML20196H524	List: ML20196H520 ML20196H529 ML20196H544 ML20196H558 ML20196H572
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NUDOCS 9907060377
Download: ML20196H558 (36)

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FINAL RADIOLOGICAL SURVEY PERFORMED AT GENERAL ATOMICS' f

BUILDING 35-1 Prepared By: Paul Maschka, Laura Gonzales, Efraim Ramirez, Scott Cowan, Undree Wells, Steve Finchum, Kim Moore, Richard Stowell and John Turner March 5,1999 9907060377 990623 00 734

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Table of Contents j

INTR ODUCTI ON............................................................... 1 S ITE DESCRI PTION............................................................ 1 PREVIOUS ACTIVITIES (HISTORY OF USE)....................................... 2 CRITERIA FOR RELEASE TO UNRESTRICTED USE................................ 3 Facilities and Equipment.................................................... 3 Exposure Rate Guideline.................................................... 3 IN STRUMENTATION........................................................... 4 B ACKGROUND MEASUREMENTS............................................... 4 Background Measurements for Instruments / Detectors

............................4 Exposure Rate Background.................................................. 5 DECOMMISSIONING ACTIVITIES IN ROOM i 16A.................................. 5 Removal of Items and Equipment............................................. 5 Removal o f Walls......................................................... 5

" Footprint" of the Wall..................................................... 6 FINAL SURVEYS PERFORMED.................................................. 6 Objectives and Responsibilities.............................................. 6 Classification of Areas.................................................... 6 Fina ! S urvey Plans........................................................ 7 S URVEY S UM M ARY........................................................... 7 RESULTS OF THE FINAL SURVEYS.............................................. 8 S c a nni n g................................................................ 8 Fixed M easurements....................................................... 8 Removable Contamination Surveys........................................... 8 Exposm e Rate Measurements................................................ 9

" Footprint" of the Walls.................................................... 9 Soil / Concrete Samples..................................................... 9 CON C LU S ION................................................................. 9 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 o f Instruments.................................................... T-3 Table 4:

Background Measurements (Obtained from Building 13)...................... T-6 Table 5:

Results of Final Surveys in Building 35-1.................................. T-8 11 l

1 List of Figures (unpaFed)

Figure 1:

Plan View ofGeneral Atomics Site i

Figure 2:

Building 35-1 in Relation to Surrounding Facilities Figure 3:

Building 35-1 Floor Plan Figure 4:

Room 116A: a/p Scans, p Fixed Measurements & Removable Contamination Locations (after removal of the Fume Hood & other contents) f Figure 5:

Room i16A (Footprint): Direct a & p Surveys & Removable Contamination Locations (after removal of the walls)

Figure 6:

Rooms 115 and 116: n/p Scan Locations Figure 7:

Rooms 115 & 116: p Fixed Measurements & Removable Contamination Locations Figure 8:

Rooms 115 & 116: Exposure Rate Measurement Locations & Results Figure 9; Non-impacted Area Surveys List of Annendirma Appendix A:" Evaluation of Radiation Surveys Performed in Building 35-1 Room 116A" dated September 4,1998.

Appendix B: " Building 35-1, Shipping and Receiving Radiation Survey Plan" dated December 11, 1997 & Supplement #1 dated September 3,1998.

iii

4-88 memes Building 35-1 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 Radiolcgical Survey of Building 35-1 located at GA's Sorrento Valley Site.

GA is requesting both the Nuclear Regulatory Commission (NRC) and the State of California for the release of Building 35 1 to unrestricted use.

This report documents the results of radiological measurements completed inside Building 35-1 and demonstrates that this area meets the approved criteria for release to unrestricted use. The total j

2 2

surface area to be released to unrestricted use is ~ 8420 ft (~ 782 m ),

Site Description l

A plan view of the GA Site is shown in Figure 1. The location of Building 35-1 in relation to other j

facilities at GA's Sorrento Valley Site is shown in Figure 2. A drawing of Building 35-1 is shown in l

Figure 3.

Building 35-1 is separated into two autonomous areas, (1) the Shipping and Receiving Department, Facilities Service Mail Room and other associated rooms and offices and (2) in the eastern portion of

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the building, GA's Facilities Engineering and Maintenance Department. These individual areas within Building 35-1 are as follows:

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Shipping / Receiving / Mail Room 6060 563 Facilities Engineering / Maintenance 2MD 212 Totals 8420 782 All of the floors within the building are composed of reinforced concrete. The concrete floors may be covered with linoleum tile or carpet within individual rooms / offices. The exterior walls of the building are composed of cormgated (standard stock) sheet metal. All of the exterior walls are attached to a stmetural steel framework and adjoin the edge / footings of the concrete floor. The exterior walls are lined on the inside with drywall / sheet rock. All interior walls (separating the i

rooms / offices, etc.) within the building are composed of drywall / sheetrock 1of9

f I

l S am m manses Building 35-1 Final Radiological Survey Report The roof consists of ribbed steel decking. The ribbed steel sheets span supporting roof rafters and I-beams to which they are fastened. The entry / exit doors as well as the roll-up doors are composed ofmetal.

Previous Activities (History of Use)

There is no known history of radioactive materials being used or stored within GA's Facility Engineering and Maintenance Departments. This area includes rooms 100 thru 109 that were used as office spaces for GA employees (see Figure 3).

Rooms 110 thru i14 and rooms 117 thm 123 within the Shipping and Receiving Department are also office spaces for the GA employees and radioactive material was never used or stored within these areas (see Figure 3).

The only history of radioactive materials being within the building was in the Shipping and Receiving Department whenever properly packaged radioactive materials were either shipped or received. The only rooms involved with the shipping and receiving of the properly packaged radioactive materials are Rooms 115,116,116A and the caged area (see Figure 3).

Room 115 The final outer packaging and subsequent shipping of radioactive materials were performed within this room. Properly sealed containers of radioactive materials were received in the Shipping Department from on-site shippers and prepared for delivery off-site. No exposed or uncovered radioactive materials were ever handled in this 2

2 room. Room 115 encompasses an area of approximately 1014 ft (~ 94 m ),

Room 116 This room was used to receive properly packaged radioactive materials being sem u GA from off-site shippers. Whenever a package containing radioactive materials was received, it was immediately placed within the caged area located in the northern portion of Room 115. A Health Physics (HP) technician would be notified ofits arrival. The HP technician would move the package from the caged area to Room 116A (located in the northern portion of Room 116), wherein the package would be subjected to the required radiological monitoring. Room i16 encompasses an area of 2

2 approximately 702 ft (~ 65 m ),

Caged Area This is a segregated area within Room 115 that was used to temporarily store packages containing radioactive materials received from off-site as well as l

temporarily store properly packaged radioactive materials that were prepared for off-site delivery. The caged area is composed of heavy gauge wire mesh on the east, 2 of 9

i 1

4 muummasmranscw Building 35-1 Final Radiological Survey Report west and south walls and metal lined along the north wall. The door to this area is equipped with a security lock. The caged area within room 115 encompasses an area 2

2 of approximately 38 ft (~ 3 % m ),

Room 116A This is a small locked room within Room 116 that was used to conduct radiological surveys on the packages and their contents received from off-site. The packages were opened by a IIP tecimician and the contents were checked for radiological containment. These activities were conducted with proper radiological controls by the use of a fume hood, IIEPA unit and associated plenum,' filters, exhaust fan and ductwork. The system was ducted to the outside through the nonh wall. This 2

2 segregated room (116A) encompasses an area of approximately 45 ft (~ 4 m ),

Room i16B This room contains the telephone and communications switching equipment. No radioactive material was ever used or stored within this area (it was included in this group due to its proximity to room 116A and the caged area). This room (116B) encompasses an area of approximately 42 ft2 (~ 4 m ),

2 Criteria for Release to Unrestricted Use Facilities and Equipment The U.S. NRC's criteria for releasing facilities and equipment to unrestricted use is shown in Table 1. The State of California's guidelines,"DilS Criteria for Release of Facilities and Equipment to Unrestricted Use," also known as "DECON-1," is shown in Table 2.

Based on the previous history of work conducted in the Shipping and Receiving Department (rooms 115 & 116) the predominant radiological contaminants were determined to be beta / gamma emitters.

The approved guideline values for release to unrestricted use for these beta / gamma emitters are pmvided below:

2 2

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

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

Egoosure Rate Guideline The guideline value for exposure rates measured at 1 m above the surface, is 10 yR/hr above background levels.

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4 8 mum m mommes Building 35-1 Final Radiological Survey Report Instrumentation A list ofinstruments used during the radiological surveys is shown in Table 3. The table includes:

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

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

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

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

A" b/I#

Equation (8-11) 1 /

Equation (8-12)

EE1 (A-#M n-1 Minimum detectable activities (MDA's) for each type of surface (see Table 4), were calculated using equation (5-2) from the NUREG/CR-5849 as follows:

8 Manual for Conducting Radiological Surveys in Support of License Termination (Draft for Comment),

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

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Samummu.mnases Building 35-1 Final Radiological Survey Report Equation (5 2) 2.71 +4.65 /B,x t(dpmil00cm ')

MDA=

txEx i

100 Where:

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

E = efficiency j

2 A = area of the detector (cm )

Exoosure Rate Backstround Typical exposure rate background for this site is about 15 R/hr meacured 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 over a period of a year also give an average of about 15 R/hr (measured at I m from the surface). Nonnal background exposure rates increase to about 22 R/hr at 1 m from the surface in small rooms with concrete floors and walls and up to 28 R/hr inside concrete lined trenches or concrete lined pits (background measurements inside a concrete pit near Building 2 confirmed this).

Decommissioning Activities in Room 116A Removal ofItems and Equipment The fume hood, HEPA unit and associated plenum, exhaust fan and ductwork in Room i16A were radiologically surveyed to determine the extent of contamination. The fume hood, HEPA unit and its intake ductwork were removed from the room and properly disposed of as radioactive waste. The exhaust fan and its ductwork were also removed from the room and disposed of as non-radioactive waste after surveys showed that no contamination was present.

The cabinet and bench within room 116A were surveyed and no contamination was detected. They were released for non-radioactive waste disposal.

Removal of Walls The walls surmunding room 116A were also radiologically surveyed and no contamination was detected. The non-structural walls were removed and disposed of as non-radioactive waste. Refer to Appendix A for the report " Evaluation of Radiation Surveys Performed in Building 35-1 (Room 116A) dated September 4,1998."

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% - mannes Building 35-1 Final Radiological Survey Report Room 116A no longer exist; its contents and walls have been completely dismantled and properly disposed of as either radioactive or non-radioactive waste as appropriate.

"Footorint" of the Walls After the walls were removed, the area on the floor that was covered by the walls (footprint) was surveyed for both direct and removable contamination. The survey results showed that no contamination was present.

Final Surveys Performed Obiectives and Resnonsibilities The objectives of the final survey plan were (1) to demonstrate that the average surface contamination levels for each survey unit were 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 clean removable contamination (i.e., masslinn wipes) and fixed contamination (if necessary) and (4) that the exposure rates in occupiable locations are less than 10 R/hr above background.neasured at 1 meter above the surface.

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

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

Classification of Areas Non-Impacted Areast The entire Facilities Engineering and Maintenance Departments (rooms 100 thru 109) have no history ofradioactive material usage. Rooms 110 thru 114 and rooms 117 thru 123 within the Shipping and Receiving Department also have no history of radioactive material usage. Therefore, they were classified as "non-impacted" areas and require no radiological surveying. However, exposure rate measurements and removable wipe (100 cm ) surveys were 2

conducted in these areas. In addition, the floor surfaces in the stairwell and the adjacent linoleum 2

tiled hallway (H01) were scanned with a 434 cm p detector. These areas are shown in Figure 3.

60f9 i

______m

4--ma manner Building 35-1 Final Radiological Survey Report Unagected Areast Rooms 115 and 116 were involved with the shipping and receiving of properly packaged radioactive materials. Therefore, they were classified as " unaffected" areas ; no contamination was expected to be present. These areas are shown in Figure 3.

Non-suspect Afected Areas: Room 116A was used as an isolation area to open and survey the packages of radioactive materials received from off-site shippers. It was classified as a "non-suspect affected" area. The caged area within room i 15 was used for the temporary storage of packages containing radioactive materials received from off-site as well as packages of radioactive materials waiting to be shipped off-site. It was also classified as a "non-suspect affected" area. These areas are shown in Figure 3.

Final Survey Plana 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-impacted, unaffected or non-suspect affected).

The surveys included large area masslinn smears, scanning of the floors and wall surfaces, collection and analyses (by gross alpha / beta counting) of 100 cm wipes, the taking of fixed measurements and 2

exposure rate measurements ( R/hr).

The surveys were completed in accordance with an approved written Final Survey Plan. A copy of the Survey Plan is provided in Appendix B to this report: " Building 35-1, Shipping and Receiving Radiation Survey Plan" dated December 11,1997 & Supplement #1 dated September 3,1998.

Survey Summary A summary of the number of fixed measurements,100 cm wipes and exposure rate measurements 2

taken during the Final Survey is provided below:

' Building 37 Final Survey Summary Survey.

1. ofFixed Measurements?

L # of100 cm. wipes

1. of Exposure Rate Measurements 2

1 A

p

. ( R/hr)

Final Survey 16 54 49 7 of 9 r

f

$ sasumm m m onecs Building 35-1 Final Radiological Survey Report Results of the Final Surveys The results for the Final Surveys are provided in Table 5 and Figures 4 through 9.

Scannine 2

Scans with a 434 cm alpha gas-flow proportional detector (floor monitor) were conducted in the unaffected and non-suspect affected areas in order to identify elevated areas of activity. Areas with elevated readings would then be further investigated with hand-held a instruments / detectors to determine if the levels were above the release criteria. No areas were discovered that displayed elevated levels of a activity. The results of these scans are provided in Table 5 and in the respective figures for each location.

2 Scans with a 434 cm beta gas-flow proportional detector (floor monitor) were also conducted in the unafEk! and non-suspect affected areas in order to identify elevated areaa of activity. Areas with elevated reaa%s would then be further investigated with hand-held p instruments / detectors to determine if the levels were above the release criteria. No areas were discovered that disniaved elevated levels of B activity. The results of these scans are provided in Table 5 and in the respective figures for each location.

Fixed Measurements A total of 16 fixed beta measurements were performed during the final survey in the unaffected and non-suspect affected areas. The final measurements were taken using a 100 cm gas-proportional 2

beta detector.

Two (2) minute fixed p measurements were taken. 'Ihe applicable background for the 100 cm beta 2

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

dpm/100 cm using the appropriate count time, the efficiency of the detector and the geometry of the detector. The results are provided in Table 5 and the approximate locations are shown in their respective fig"res. All fixed p measurement results were less than the MDA for the respective surfaces surveyed (see Table 4 for MDA results in dpm/100 cm for each surface surveyed).

2 Removable Contamination Surveys 2

A total of 54100 cm wipes were taken during the final survey. The wipes consisted of using a 2

2 Whatman Filter Paper (4.7 cm diameter) and wiping an area of ~ 100 cm. The wipes were counted in GA's Health Physics Laboratory using a Canberra 2400 low level alpha / beta counting system.

2 The wipe results in dpm/100 cm for both alpha and beta are provided in Table 5 and shown in their respective figures. The maximum wipe results within the building were l'. dpm/100 cm a and 21 2

2 dpm/100 cm p, 8 of 9

.$ - - masses Building 35-1 Final Radiological Survey Report The maximum wipe results in the non-impacted areas were < 10 dpm/100 cm a and < 10 dpm/100 2

2 cm p. The maximum wipe results in the unaffected portions of the building (rooms 115 & 116) 2 2

were 17 dpm/100 cm a and 19 dpm/100 cm p. The maximum wipe results in the non-suspect affected areas (room i16A & the caged area) were 17 dpm/100 cm a and 21 dpm/100 cm p, 2

2 Large area masslinn surveys were also conducted on the unaffected and non-suspect affected area floors by wiping the surfaces with masslinn cloths and measuring the activity on the cloths with a 2

hand-held 15 cm GM pancake detector. All readings were s to background levels.

Exposure Rate Measurements A total of 49 direct radiation exposure rate measurements were taken at various locations inside the facility. The measurements were taken at ~1 meter above the surface using a microR meter. The exposure rate measurements are provided in Table 5 and in the respective figures for each location.

Exposure rate measurements inside the facility in the non-impacted areas ranged from 11 to 15 R/hr. Exposure rate measurements of the unaffected portions of the building ranged from 12 to 15 R/hr. Exposure rate measurements in the non-suspect affected areas (room 116A & the caged area) ranged from 14 to 15 R/hr.

"Footorint" of the Walls The remaining " footprint" of the walls was surveyed (100%) with a 15 cm GM pancake detector 2

and all readings were s background levels. The footprint was also surveyed (100%) with a 50 cm2 h

alpha detector and all readings were s to background levels. A total of 10 wipes (100 cm ) were 2

taken from the footprint to determine removable contamination levels and the maximum wipe results 2

2 were < 10 dpm/100 cm a and 10 dpm/100 cm p. The results are provided in Table 5 and the approximate locations are shown in Figure 5.

Soil / Concrete Samnles No sampling of the concrete or soil beneath the concrete was required since there was no radioactive contamination detected on any of the floor surfaces or walls.

Conclusion Final contamination and radiation surveys provided in this report for Building 35-1 demonstrate that the building meets the approved guidelines for release to unrestricted use.

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Table 1: USNRC'S ACCEPTABLE SURFACE CONTAMINATION LEVELS '

Nuclides' AverageW MaximumW RemovableW 2

(dpm/100cm )

(dpm/100 cm')

(dpm/100cm')

U-nat, 235U,23sU, & associated decay products 5,000 a 15,000 a 1,000 a Transuranics,226Ra,22:Ra, 230Th, 22sTh, 23 Pa, 100 300 20 327Ac, i25g, :29g Th-nat, 232Th, "Sr, 223Ra, 224Ra, 232U, i26j, i33,

1,000 3,000 200 1

131i Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except "Sr and other noted above.

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

established for alpha-and beta / gamma-emitting nuclides should apply independently, b

As used in this table dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency and geometric factors associated with the instrumentation.

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

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

2 d

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

2 e

The amount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects ofless surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.

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

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

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

T-1

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l Table 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS 8 Nuclides*

AverageW MaximumW Removabled 2

2 2

(dpm/100cm )

(dpm/100cm )

(dpm/100cm )

U-nat,235U,23sU, & associated decay products 5,000 15,000 1,000 Transuranics,226Ra, 228Ra, 23 Th, 22sTh, 23'Pa, 100 300 20 227Ac, 25g, :29g Th-nat, 232Th, "Sr, 223Ra, 224Ra, 232 U, 26, 333,

1,000 3,000 200 I

1 131J Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except "Sr and other noted above.

a Where surface contamination by both alpha-and beta / gamma-emitting nuclides exists, the limits established for alpha-and beta / gamma-emitting nuclides should apply independently.

b As used in this table dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correcting the counts per minute observed by an appropriate detector for background, efficiency and geometric factors associated with the instrumentation.

c Measurements of average contaminant should not be averaged over mo e than I square meter. For objects of less surface area, the average should be derived for each such object.

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

2 e The arnount of removable radioactive material per 100 cm of surface area should be determined by wiping that area with dry filter or soft absorbent paper, applying moderate pressure, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known efficiency. When removable contamination on objects ofless surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.

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

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.

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Ludlum Model 2221 Ratemeter s/n 97287 with Model 43-37 Probe s/n 086238 Alpha Floor Monitor Backgrolund Scan Results: 434 cm Detector (Efficiency = 20.21%)

2 h

Backgr:.und Material p

Alpha Scan Range (epm)

Conecte 0-20 Drywall /Shectrock 0-15 Metal 0-20 Ludlum Model 2221 Ratemeter s/n 73701 with Model 43-37 Probe s/n 083265 Beta Floor Monitor Background Scan Results: 434 cm Detector (Efficiency = 20.30%)

2 Background Material Beta / Gamma Scan Range (cpm)

Concrete 1795-2030 Drywall / Sheetrock 906-1050 Metal 1151-1425 Ludlum Model 2221 Ratemeter s/n 86302 with Model 43-37 Probe s/n 086215 h

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

2 Background Material Beta / Gamma Scan Results (cpm)

Concrete 1276-1530 Drywall /utteetrock 693-951 1

Metal 853-1185 i

Ludlum Model 2221 Ratemeter s/n 148436 with Model 43-68 Probe s/n 142540 2

100 cm Beta Detector (Efficiency =27.06% )

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2 Concrete 1011 48 212 T-6

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Tcble 4: Backgrcund Me:surements (Obtained from Building 13)

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1. Survey results are provided in Table S.

2. als scans are located in the cross hatched areas.

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3. The numbers within the circles are the approximate locations of the removable contamination wipes (100 cm2).

4. The squares with the cross hatches are the approximate locations of the fixed p measurements taken.

5. All concrete & drywall / sheetrock surfaces.

L

l Figure 5: Room 116A (Footprint). Direct a & p Surveys & Removable Contamination Locations (after removal of the walls).

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i l +_I NOTES.

1. Survey results are provided in Table 5.

2. Direct n/D surveys were conducted on the " footprint" that was previously covered by the walls.

3. The numbers within the circles are the approximate locations of the removable contamination wipes (100 cm2).

4. All concrete surfaces.

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Appendix A to Final Radiological Survey Performed at General Atomics' Building 35-1

" Evaluation of Radiation Surveys Performed in Building 35-1 Room 116A" dated September 4,1998

Evaluttion of Radiction Surveys l

Performed in Building 35-1 Room 116A

)

l September 4,1998 The surveys were done according to the Radiation Survey Plan dated December 11,1997.

Survey sheets included the location and dates of the survey. The Health Physics Technician's name and signature, results of the surveys, and data for the instruments that were used (including calibration due date).

100% of the floor surface was scanned with the 434 cm probe for both beta / gamma and 2

alpha. No contamin~ ation was found in the facility except for contamination inside the hood in 116A. The hood was removed and placed in radioactive waste.

50% of the wall surface up 2 meters was scanned with the 434 cm probe for both beta / gamma and alpha. No contamination was found.

Smears results were <25 dpm/100cm for both alpha and beta, well below the release 2

criteria.

Two minute direct radiation measurements were all <MDA of 268 dpm/100 cm2, well

)

)

below the release criteria.

Exposure dose rate su:vey showed radiation levels at or near background,12-15 pR/hr.

Based on the following the walls of the room 116A may be taken down and disposed of as' non radioactive waste.

l.

The results of the scans performed on the floor and walls demonstrates that no contamination was present and the radiation levels were all below the release criteria.

2.

The direct measurements were all <MDA.

3.

The smears were all <25 dpm/100 cm2, 4.

The exposure dose rate levels were at or near background levels.

5.

The area on the floor that is covered by the wall will be surveyed for both direct and removable contamination after the walls are removed.

6.

These walls are non-structural walls.

Evaluated by dbl /so Date 9 - V-f7 Paul R. Maschka cc:

K. Asmussen F. Dahms I

L. Gonzales J. Sullivan C. Taylor CMAANDlaD235 ITEVAL351.TLE

Appendix B

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to Final Radiological Survey Performed at General Atomics' Building 35-1

{

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" Building 35-1, Shipping and Receiving Radiation Survey Plan" dated December 11,1997 &

Supplement #1 dated September 3,1998 L

I BUILDING 35-1, Shipping and Receiving Radiation Survey Plan Paul R. Maschka December 11,1997

[a~ /d M A dA The area covered by this survey plan includes Rooms 115,116,116A, and the Cage l

area in room 115.

l 2

2 Total area is 1526 ft (142 m )

Historical Use 2

2 Room 116A [36.6 ft (3.4 m ))

This area contains a hood equipped with a HEPA exhaust system and a bench.

Packages of radioactive materials are opened and surveyed in this area.

Room 116B This room contains the telephone and communications switching equipment.

2 2

Cage Area [38.9 ft (3.6 m ))

This caged area is used to store packaging materials and containers with radioactive materials that are received from off site and packages of radioactive materials that are prepared for shipment.

Room 115 Packaging and shipping operations are performed in this room. Radioactive materials that are shipped from this room are received in sealed containers from the shipper, therefore, no sposed or uncontained radioactive materials were handled in this room.

Room 116 This is the area where packages being sent to General Atomics are received. When a package containing radioactive materials is received, it is immediately placed in a caged area located in Room 115 and Health Physics is notified of the arrival of the package within three hours. The HP technician goes to the caged area and moves the package to Room 116A where he performs the required radiation monitoring of the package.

Rooms 116, and 115 are unaffected areas. Room 116A and the Caged area are non-suspect affected areas.

l

[

Radiation Survey Plan ROOM 116A 1.

Complete a radiation and contamination survey on the bench, hood, and exhaust system in and on top of Room 116A. Decontaminate as required and prepare the bench, hood, and exhaust system for removal.

2.

Scan 100% of the floor for beta / gamma and alpha using the floor monitors.

3.

Scan 50% of the walls up 2 meters for beta / gamma and alpha using the floor monitors.

4.

Take 4 fixed measurements,2 minutes each beta only, on the floor, one in each quarter.

5.

Take 4 smears on the floor, one in each quarter.

6.

Take 4 smears on the walls, one on each wall.

CAGED AREA 1.

Scan 50% of the floor for beta / gamma and alpha using the floor monitors.

2.

Scan 10% of the walls up 2 meters for beta / gamma and alpha using the floor monitors.

3.

Take 2 fixed measurements,2 minutes each beta only, on the floor.

4.

Take 2 smears on the floor.

ROOMS 115/116 1.

Scan 100% of the floor for beta / gamma and alpha using the floor monitors.

2.

Scan 100% of the walls up 2 meters for beta / gamma and alpha using the floor monitors.

3.

Take 6 fixed measurements,2 minutes each beta only, on the floor, evenly spaced.

4.

Take 20 smears on the floor, cabinets, tenches, and storage racks, evenly space d.

5.

Spot check cabinets, benches, and storage racks with hand held GM pancake detectors.

r BUILDING 35-1, Shipping and Receiving Radiation Survey Plan Supplement 1 fdfN4WY P l R. Maschka September 3,1998 AMitinnal Survey Take exposure rate measurements in Rooms 115,116,116A, and the Cage area in room 115 using a microR dose rate instrument. Take one measurement every 7 meters.

Drw omentation Every radiological survey conducted must be documented on a daily basis to a worksheet/ log book and on a drawing showing the appropriate locations surveyed. The documentation must include the results of the measurements (including units), the technician's printed name and signature, date, instrument (s) used (including the model and serial number of both the ratemeter and the detector), calibration due date, % efficiency, background readings (if applicable) and any other pertinent information.

I i

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