ML20237C622

Final Radiolgical Surveys of Selected Bldg 2 Labs for Release to Unrestricted Use Group 10

ML20237C622
Person / Time
Site:	07000734
Issue date:	08/13/1998
From:	Bell A, Gonzales L, Keesling D GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML20237C620	List: ML20237C618 ML20237C622
References
NUDOCS 9808240029
Download: ML20237C622 (36)

Text

- _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ - - _ _ _ _.__

i CENERAL ATOMICS FINAL RADIOLOGICAL SURVEYS l

OF SELECTED BUILDING 2 LABORATORIES FOR RELEASE TO UNRESTRICTED USE j

l l

" GROUP 10" l

l August 13,1998 Prepared By: Dan Keesling, Laura Gonzales, Aaron Bell, Undree Wells and Paul Maschka, 9808240029 980814 PDR ADOCK 07000734 C

PDR 4

v_ _ _ _ _ _ _ __ _ - _ _

I l

l

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I TABLE OF CONTENTS l

Pace l

LIST OF TABLES

..................................................ii

- LIST OF FIGURES

.......................................iii INTRODUCTION........................

....... 1 SITE DESCRIPTION

.1 CRITERIA FOR RELEASE TO UNRESTRICTED USE

.. 2 PREVIOUS ACTIVITIES (HISTORY OF USE)...................

........ 2 l

l INSTRUMENTATION

... 2 BACKGROUND MEASUREMENTS

.....3 SU RVEY PLAN......................

... 3 i

DECONTAMINATION...................

......... 4 RESULTS OF THE FINAL SURVEYS.....

... 4 Scanning........................

..... 4 Fixed Measurements.................

5 Removable Contamination Surveys.....................

.......... 5 l

Exposure Rate Measurements..................

..... 5 GA INTERNAL CONFIRMATORY SURVEY................................. 6 l

Scans...............................

......6 Direct Measurements

.......... 6 Removable Contamination Surveys..................

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

]

CON C LU SION......

6 TABLES...............................

.......... 7 i

FIGURES........................................

........ 21 l

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___.-.___._m___

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_______.____m_

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J.lST OF TABLES Paae Table 1:

USNRC's Acceptable Surface Contamination Levels.......

.8 Table 2:

State of CA Acceptable Surface Contamination Levels 9

Table 3:

List of instruments......

.............. 10 Table 4.

Background Measurements and MDA'S........

.... 12 Table 5:

Results of Radiation Scans and Fixed Measurements.

.13 Table 6A:

Exposure Rate Measurements - Group 10 Labs.

.... 18 Table 6B:

Background Exposure Rate Measurements

.. 18 Table 7:

Results of Removable Contamination Surveys

.19 Table 8:

Results of GA's Internal Confirmatory Survey.......

... 20 I

ii

Group 10 l

l LIST OF FIGURES l

Page Figure 1:

General Atomics Site

.... 22 l

Figure 2:

Building 2 Laboratory Locations...................

......... 23 Figure 3:

Building 2 Lab 202 Final Survey...

......................... 24 Figure 4:

Building 2 Lab 204/206 Final Survey...........

25 Figure 5:

Building 2 Lab 208 Final Survey..............

.26 Figure 6:

Building 2 Lab 210 Final Survey....

. 27 Figure 7:

Building 2 Lab 409 Final Survey..

.28 Figure 8:

Building 2 Lab 605 Final Survey 29

{

Figure 9:

Building 2 Lab 605 initial Survey....

... 30 Figure 10:

Building 2 Lab 607 Final Survey........

.. 31 Figure 11:

Building 2 Lab 617 Final Survey 32 I

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l l

L_________________-____--_______--_____---

l Group 10 INTRODUCTION l

General Atomics (GA) is continuing its efforts directed at decontaminating, as appropriate, and obtaining the release to unrestricted use of selected laboratories and associated offices in GA's Building 2 (also known as the Science Laboratories Building or "L" Building). The building was built in 1958 for purposes of conducting research and development activities. To date, nine (9) groups of labs in this building have been decontaminated and released to unrestricted use.

GA has recently surveyed additional laboratories in Building 2 designated as " Group 10". This report summarizes the surveys completed for the " Group 10" laboratories which consist of nine (9) 2 labs and a total area of 2392 ft,

Contamination (Cs-137) was detected in only one small area (~15 cm ) of one lab (Lab 605). No 2

contamination was detected in any other " Group 10" lab.

GA has no plans for conducting any future activities involving radioactive materials in these laboratories and/or mezzanines. (The offices across the hall from these laboratories have never been used for work involving radioactive materials). This report documents the results of extensive and comprehensive measurements completed in Building 2 " Group 10" Laboratories to demonstrate that these laboratories, meet the approved criteria for release to unrestricted use. Accordingly, GA is requesting that these laboratories and their associated offices be released to unrestricted use.

I l

SITE DESCRIPTION The location of Building 2 with respect to other facilities on the GA Site is shown in Figure 1. A layout of Building 2 and the location of each " Group 10" laboratory is shown in Figure 2. The nine (9) laboratories are 202,204/206,208,210,409,605,607,617. Labs 204/206 are a combined lab.

2 Only lab 617 has a mezzanine but it was released with " Group 3". The total area is 2392 ft,

l Lnk ft

• d 202

-324

~30 l

204/206

-312

-29 208

-324

-30 210

-328

-30.5 409

-204

-19 605

-288

~26.6 607

-288

-26.6 617

_324

-JQ Total 2.392

-222 1

l l

+M ome to CRITERIA FOR RELEASE TO UNRESTRICTED USE Table 1 is taken from U.S. NRC's criteria for releasing facilities and equipment to unrestricted use.

It has been incorporated into GA's SNM-696 license. The State of Califomia's guidelines, "DHS Criteria for Release of Facilities and Equipment to Unrestricted Use," also known as "DECON-1," are summarized in Table 2.

PREVIOUS ACTMTIES (HISTORY OF USE)

GA's Work Authorization logs were searched in order to review the previous activities conducted in cach lab and to identify the radionuclides of concem. Information obtained from the' logs demonstrated that detailed measurements in each lab were needed. Only two of the nine labs in Group 10 have a history of radioactive materials usage (lab 409 and lab 605). The other seven labs had no history of use involving radioactive materials. The following is a brief summary of the activities l

performed in each lab and the classification of the lab based on history.

Lab 202 No history of radioactive materials use - an " unaffected area."

Labs 204/206 No history of radioactive materials use - an " unaffected area."

Lab 208 No history of radioactive materials use - an " unaffected area."

Lab 210 No history of radioactive materials use - an " unaffected area."

Lab 409 Beginning in the early.1970's through 1986, this lab was used to perform chemical and spectrographic analyses on materials containing uranium and thorium in order to identify composition by counting techniques (WA #2010). It was categorized as a

" suspect affected" area.

Lab 605 This lab's history included the grinding, screening, sensitometric analysis and cutting of irradiated graphite beginning around 1968 until the early 1970's. It was categorized as a " suspect affected area".

Lab 607 '

No history of radioactive materials use - an " unaffected area."

Lab 617 No history of radioactive materials use - an " unaffected area."

INSTRUMENTATION l

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

. description of the instrument, (2) the model and serial numbers of the meters and detectors, (3) instrument ranges, (4) calibration due dates, (5) typical efficiencies, and (6) typical background count rates, 2

i l

kE Group 10 BACKGROUND MEASUREMENTS

}

Five (5) types of surfaces exist in Building 2 " Group 10" Labs. These surfaces are tile over concrete.

l concrete, concrete block, dry wall and wood. Building 13 was selected for conducting background measurements due to the age of the building, because radioactive material has never been used in this building, and the various surfaces found in Building 2, could also be found in Building 13.

The fixed background measurements are shown in Table 4. The mean and standard deviation for 2

l each surface surveyed with th) 100 cm detector were calculated using equations 8-11 and 8-12 from l

NUREG/CR-5849 as shown beJow:

Equation (811):

2 1E'.',1, Equation (812):

E", G-xf

• ~s n.,

Background measurements and minimum detectable activities (MDA's) for each type of surface and for various counting times are also provided in Table 4. Minimum detectable activities (MDA's) for gach type of surface, were calculated using equation (5-2) from NUREG/CR-5849 as shown below:

l Equation (6 2)

I 2.71 +4.65/B,x t 2

MDA=

(dpm/l00cm )

^

txEx 100

%here:

Ba= background rate (cpm)

! = count time (min)

E = efficiency A = area ofthe detector (cm ')

SURVEY PLAN A survey plan (s) which documented the types of surveys to be performed and the locations was developed based upon the physical characteristics of the lab, the radioactive material used and the f

potential for contamination. The physical characteristics of the labs include the consideration of

(

vents, ducts, whether surfaces are painted or unpainted, overhead structures, floor coverings, etc.

l 3

i

+M croup io l

Types. of surveys performed include scanning, exposure rate measurements and ' survey measurements (wipes and fixed measurements).

DECONTAMINATION L

Characterization surveys showed no detectable contamination except in lab 605 where two areas of elevated radiation levels were identified (see Figure 8 for characterization survey)..

L The first area (~15 cm ) measured 5,000 - 10,000 cpm ( ~141,300 dpm/100 cm - 282,600 dpm/100 2

2 l

cm ) using a geiger counter (with a pancake GM detector) (see Figure 8).' The radionuclides was 2

l.

~ identified as Cs-137. The area was decontaminated with a mechanical scabbling device. The area was surveyed after decontamination to background levels using the pancake GM detector (~100 cpm 2

or ~1500 dpm/100 cm ).

The second area measured only background readings using a geiger counter (with a pancake GM

[

detector) but the exposure rate reading on the concrete surface was elevated at 28 pR/hr (14 pR/hr l

at 1 m). Exposure rate readings on the surface of the concrete in other locations in the lab ranged j

from 13-15 pR/hr. The area was scabbled and the exposure rate reading did not decrease. A L

jackhammer was used to remove the 4" thick concrete floor which revealed a room below. Three l

smoke detectors (which were about 6" from the floor of lab 605) were found on the top shelf of a cabinet in the room below. These smoke detectors were causing the elevated exposure rate l

readings. The smoke detectors were moved to a lower shelf and the elevated levels decreased to l

. normal background levels.

No other labs required decontamination.

RESULTS OF THE FINAL SURVEYS L

Scanning 2

Scanning was performed in each lab using a floor monitor having a 434 cm gas-flow proportional detector, in each area where tile was present, the tile was scanned over 100% of the surface. Then the tile was removed for the final survey. The walls in lab 607 were scanned using a floor monitor 2

with 'a 100 cm gas-flow proportional detector.

For the affected areas (labs 409 and 605),100% of the concrete floor surface and the lower v911s (below 2 m) were scanned for beta activity. In addition, for lab 409,100% of the concrete floor surface was scanned for alpha activity. Lab 605, which had only a history of irradiated graphite material and Cs-137 contamination was not surveyed for alpha activity. Upper walls were not scanned ' (no suspect contaminated surfaces).

4

hM Group 10 For unaffected areas (labs 202,204/206,208,210,607 and 617),100 % of the concrete floors were scanned for beta activity. At least 25% of the concrete floor surfaces were scanned for alpha activity, except lab 607 (no history of alpha emitters used in this lab). Between 10-25% of the lower walls (below 2 m) were scanned for beta activity. Upper walls (above 2 m) were not scanned (no suspect contaminated surfaces).

The results of the scans on the floors and lower walls are provided in Table 5. Readings were at or near background levels (see Table 4 for background levels) in all labs except Lab 605 (which was at background levels shr decontamination).

Fixed Measurements Fixed measurements were performed using a beta gas-flow proportional counter having a 100 cm2 detector. The counting time for fixed measurements was two (2) minutes in all labs except for the measurements taken in lab 605 after tile removal, which were one (1) minute counts. For fixed measurements, an appropriate background was determined for each type of surface and subtracted from the survey readings. The readings were converted to dpm/100 cm using the efficiency of the 2

detector.

The fixed measurements are provided in Figure 3 for lab 202, Figure 4 for lab 204/206, Figure 5 for lab 208, Figure 6 for lab 210, Figure 7 for lab 409, Figure 9 for lab 605, Figure 10 for lab 607 and Figure 11 for lab 617. All fixed measurements are summarized in Table 5. A total of 139 fixed measurements were taken. The results show that radiation levels were well below the release criteria and in all cases were below 1000 dpm/100cm (the maximum activity detected was 388 2

2 dpm/100 cm ),

Removable Contamination Surveys Removable contamination rneasurements (smears) were performed on all surfaces including the floors, walls, overhead structures, ducts, lights and support beams. Smear surveys consisted of using a Whatman Filter Paper (4.7 cm diameter) and wiping an area of ~100 cm. The smears were 2

counted in GA's Health Physics Laboratory using a Canberra 2404 low level alpha / beta gas flow proportional counter.

A total of 180 smears were taken. The approximate locations where smears were collected are shown in Figures 3-11. The results of all removable contamination surveys are provided in Table 7.

Removable contamination levels were below the release criteria (alpha and beta results were <15 2

dpm/100 cm ),

Exoosure Rate Measurements Direct radiation exposure rate measurements using a microR meter were taken in every room at randomly chosen areas. A total of 71 measurements were taken. The radiation levels ranged from 13 - 18 R!hr, which are at or near normal background radiation levels as shown in Table 6A.

Background measurements are provided in Table 6B.

5

hM Group 10 GA INTERNAL CONFIRMATORY SURVEYS After all final surveys were completed, spot check " confirmatory" surveys were conducted by two (2)

Health Physics Technicians who was not responsible for conducting any of the final surveys. These surveys included scans and spot checks of the floors and walls using a floor monitor, a geiger counter and a hand-held alpha counter. In addition, smears were collected in random locations.

The results of all measurements are summarized in Table 8. The results show all levels were below the release criteria.

Scans About 10% of the floors were scanned using the 434 cm gas flow proportional counter. Spot 2

check scans on the walls along the floor (the bottom portion of the walls) were also performed using the same instrument. The results showed only background beta activity levels (see Table 8).

Direct Measurements Geiger counters (pancake GM detector) and hand held alpha counters (50 cm ) were used to check 2

cabinets, floor cracks, and other surfaces. The results showed only background levels (see Table 8).

Removable Contamination Surveys 2

Smears (100 cm ) were collected (5-6 smears in each lab) in random locations including the floors, ducts, light fixtures and I-beams and counted on a low-level alpha / beta proportional counter. The 2

2 results were all <10 dpm/100 cm alpha and < 10 dpm/100 cm beta (see Table 8); well below the release criteria.

CONCLUS1QR Final contamination and radiation surveys provided in this report, demonstrate that the labs, designated as " Group 10",

meet the NRC-and State-approved guidelines for release to unrestricted use.

6

Group 10 1

TABLES 7

hE Group 10 Table 1: USNRC'S ACCEPTABLE SURFACE CONTAMINATION LEVELS '

l Nuclides Average * *'

Maximum 8' Removable ^'

6 6

2 2

2 (dpm/100cm )

(dpm/100cm )

(dpm/100cm )

U-nat. 23s0,23sU, & associated decay products 5.000 a 15.000 a 1,000 a Transuranic, 22sRa, 22 era, 2 Th, 22sTh, 23'Pa, 100 300 20 22rge,1253, $2s; Th-nat,232Th "Sr,223Ra, 224Ra, 232U,12s;, 5321. ' 'l 1.000 3.000 200 Beta / gamma emitters (nuclides with decay modes other than alpha emission or 5,000 15,000 1,000 spontaneous fission) except "Sr and other noted above.

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

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

c Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area the average shou!d be denved for each such object.

d The maximum contamination level applies to an area of not more than 100 cm8 e The amount of removable radioactive matenal per 100 cm8 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 efficency. When removable contamination on objects of less surface area is determined, then pertinent levels should be reduced proportionally and the entire surface should be wiped.

f The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should no exceed 0.2 mrad /hr at 1 cm and 1.0 mrad /hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeterof totalabsorber.

' Guidelines For Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses For byproduct, Source, or Special Nuclear Material. USNRC, July 1982, incorporated into GA's SNM 696 license 8

h@

Group 10 Table 2: STATE OF CA ACCEPTABLE SURFACE CONTAMINATION LEVELS 5 Average">

Maximum">

Removable"'

2 2

2 (dpm/100cm )

(dpm/100cm )

(dpm/100cm >

U-nat, assU, 828U, & associated decay 5,000 15,000 1,000 products Transuranic,22 era,22 era,23 Th, 22eTh, 100 300 20 22'Pa. 227Ac.12sj, $29; Th-nat, 222Th, "Sr, 22'Ra, 2Ra, 222U, '2eg, $23,

1,000 3,000 200 1

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

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

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

c Measurements of average contaminant should not be averaged over more than 1 square meter. For objects of less surface area, the average should be derived for each such object.

d The maxinium contamination level applies to an area of not more than 100 cm 8 The amount of removable radioactive material per 100 cm of surface area should be determined by 2

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

f The average and maximum radiation levels associated with surface contamination resulting from beta-gamma emitters should not exceed 0.2 mrad /hr at 1 cm and 1.0 mrad /hr at 1 cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.

Guidehnes For Decontamination of Facilites and Equipment Prior to Release for Unrestricted Use or Termination of Licenses For byproduct Source, or Special Nuclear Matenal, also known as "Decon-1" incorporated into GA's State of CA Radioactive Materials Lic,nse.

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100 cm' beta detector - measurements done 1/19/98 l

Model 2221 ratemeter sm 84423 probe s/n 11E444 (efficiency 35.5%)

l Background Material Average of 10 measurements MDA (1 minutes each) total counts i 2 SD (dpm/100 cm')

Concrete 502i40 301 Concrete E..or.k 412152 274 Drywall 27.'i 22 224 100 cm' beta detector - measurements done 1/19/98 Model 2221 ratemeter s/n 84423 probe s/n 119444 (efficiency 35.5%)

Background Material Average of 10 measurements MDA (2 minutes each) total counts 12 SD (dpm/100 cm )

2 Concrete 1011i 48 298 Concrete Block 803164 272 Drywall 5421 61 219 100 cm' beta detector - measurements done 1/19/98 Model 2221 ratemeter s/n 148436 probe s/n 120477 (efficiency 27.06%)

Background Material Average of 10 measurements MDA (2 minutes each) total counts i 2 SD (dpm/100 cm')

Linoleum over concrete 613 i 28 306 Concrete 933128 376 Concrete Block 802128 349 Drywall 510130 279 Wood 719i60 331 8

434 cm Floor Menitor Background Scan Results Surface Beta / gamma Scan Range (cpm)

Beta / gamma Scan Range (cpm) s/n 73701 done 4/13/98 s/n 86302 rione 4/14/98 Concrete 1795-2030 1276-1530 Concrete block 1281-1554 1253-1538 Drywall 906-1050 693-951 Linoleum over Concrete 867-1134 2

434 cm Alpha Floor Monitor Background Scan Results Range frorr 0-20 cpm (all surfaces) 12

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fM croup io Table 6A: Exposure Rate Measurements in " Group 10" labs Location Figure Number of Range of Exposure Rate Measurements Measurements (pR/hr) l at 1 Meter from the surface Lab 202 3

11 15-18 Lab 204/206 4

11 15-18 Lab 208 5

13 14 -17 Lab 210 6

9 15-18 Lab 409 7

5 13-15 Lab 605

• 9 6

14 -15 Final Survey Lab 607 10 6

14 - 17 Lab 617 11 10 14 - 16 The initial exposure rate survey in Lab 605 showed elevated pR/hr readings on Surface of the concrete (14 pR/hr at 1 m). Source traced to 3 smoke detectors stored on the highest shelf of a cabinet in the room below (~ 6" from the ceiling of lab 605). Levels decreased to 14 pR/hr on the surface after removal of the smoke detectors.

Table 6B: Background Exposure Rate Measurements Location /

Number of Range of Exposure Rates Type of Surface Measurements at 1 Meter (pR/hr)

Breezeway and sidewalk outside 5

11 - 14 building by lab 534 Outside Building 13 (near concrete floors 1

20-21 and concrete block walis)

Outside Building 13 (near stairwells) 5 14-19 18

hE Group 10 Table 7: Results of Removable Contamination Surveys Removable Activity Measurements Number of Figure Maximum Activity Total Number of Smears on each Surface (dpm/100 cm')

Smears Alpha Beta Lab 202 11 Floor 9

Overhead Structures 3

28 13 10 8

Wall Lab 204/206 4

26

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26

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<10 Lab 210 10 Floor 6

26

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Floor

<10 7

10

<10 6

Overheads & walls Lab 605 Initial Survey 4

Floor

<10 6

Ceiling 8

20

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or 9

14

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Lab 607 4

Floor

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<10 6

Wall Lab 617 12 Floor

<10 11 20

<10 8 Wall 19

+ ".'.""at croup io Table 8: GA Internal Confirmatory Surveys Scan with Geiger Alpha Removable Contamination Surveys 2

434 cm Counter Counter Laboratory floor Readings Readings Maximum Activity monitor (cpm) (2)

(cpm) 91 No. of (dpm/100cm")

(cpm) "3 Smears Alpha Beta Lab 202 51600 60-80 0

5

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6

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6

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6

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6

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Background readings for a beta 434 cm2 gas flow proportional counter on concrete typically ranges from 1200-2000 cpm.

'2' Background readings for a geiger counter are typically < 120 cpm.

(2)

Background readings for an alpha counter are typically < 10 cpm.

20

Group 10 I

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Figure 4:

Building 2 Labs 204/206 Final Survey

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Figure 5: Building 2 Lab 208 Final Survey

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CB = Concrete Block 26 i

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Figure 6: Building 2 Lab 210 Fin:1 Surysy i

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Figure 7: Building 2 Lab 409 Final Survey

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Figure 8: Building 2 Lab 605 Initial Survey h

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Figure 9: Building 2 Lab 605 Final Survey b

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Fourteen (14) 100cm wipes were taken (108 in circles). Seven (7) exposure rates were taken.

CB = Concrete Block DW = Dry Wall Exposure rate measurements (pR/hr) taken -im frorr. surface.

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30 t

i Figure 10: Building 2 Lab 607 Final Survey

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Figure 11: Cullding 2 Lab 617 Finst Surycy EA 8

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