ML19332C831

Decontamination of Selected Ga Science Labs for Release to Unrestricted Use Addendum to Group 3 Rept

ML19332C831
Person / Time
Site:	07000734
Issue date:	09/22/1989
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:
Shared Package
ML19332C830	List: ML19332C829 ML19332C831
References
NUDOCS 8911290055
Download: ML19332C831 (39)

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DIDONTAMINATICE OF SEIJDC'IED GENERAL A104ICS' 1:

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SCIENCE IABOEUGURIES PCR RELEASE

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'IO UNRESTRICIED USE t

NHNDCM 20 " CROUP 3" REEMT DMED DECEMIER 21, 1988

(' IBIS REEWT AMMi IAB 315 Ate RXM51 Jte 2 W IAB 309) l' 1

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Septatber 22, 1989 i

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8911290055 891017 ADOCK07000,g4

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s-TABIE OF CQfITNPS Page-LIST OF ATDCHMENI'S....................................... i IN2000CTICN............................................ ~.1 S IE DESCRIPTION.. '........................................ 3 '

TARGET CRITERIA PCR RE!2ASE 20 UNRESTRICED RELEASE....... 4 -

Facility and Equipnent............................. 4 soil Criteria......................................

4 INSTRUMENTATICE AND MEASURENENT LIMITS FOR RELEASE........ 5 PREVIOUS LABORATORY ACTIVITIES........................... 6 FINAL RADIATICH SURVEYS................................... 10

. FINAL CONDEINATION SURVEYS............................... 11 OCHPLIANCE WI'IH EE TAMET CRIERIA....................... 11 OCNCLUS ICN................................................ 12 REFERENCES................................................ 13 -

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LIST OF ATTACHMENTS At+e hmant 1:

Prelintinary survey of Laboratory 315 f

At+ ehmant 2:

Preliminary survey of Laboratories 307/309 (2 pages)

Atte hmant 3:

Plan View of Site.

Atte hmant 4:

Building 2 cm plex (Science Laboratories Building)

At+ e hmant 5:

Selected Science Labs (AManein= to Group 3) to be Released to Unrestricted Use i A:

Table I Guidelines 'for Release of Equipnent and Facilities to Unrestricted Use (NRC) i Atte hmant 6B:

Table I Guidelines-for Release of Equipnent and Facilities to Unrestricted Use (State of California Decon-1) C:

Criteria for Soil Decontamination at the GA Site Attehmant 6D:

Soil Concentrations Resulting in an Inhalation Dose'above the Target Criteria Attehmant 7:

Final Radiation Survey of Lab 315 t

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Drawing showing Lab 309 Roans and Iab 307 and Drain Lines :

Initial Survey of Roans 1 and 2 of Cabined Labs 307/309 0:

Initial Soil Su ple I4 cations At+e hmant 11:

Initial Soil Se ple Results Attehmant 12:

Final Soil Se ple locations Att e hmant 13:

Final Caposite Soil Suple locations' Atte hmant 14:

Final Soil Suple Results-(Individtml and Caposite) (3 -

pages) f At+ e hmant 15:

Contamination Survey Results'

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INI'RODUCTICE l

j General Atcmics has been involved in the gvce8s of decontaminating and ottnining the release to unrestricted use of salected laboratories and associated offices in GA's Bn41Mng 2 (also known as the science u

Imboratories Building). A nunber of laboratories were released earlier p

th3s year in two groups designated as " Group 1" and " Group 2".

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involved the release of twenty-five (25)~ laboratories and Group 2 involved p

the release of thirteen (13) laboratories.

In addition, another group of laboratories have been decontaminated; this group has been designated as

" Group 3".

" Group 3" consists of fifteen (15) laboratories (12 of these f

laboratories have mezzanines) and nine (9) other mez uninan located above lahnratories which are not being released at this time. 'Ibese later laboratories are currently occupied; however, none of the activities involve the use of radioactive material.

On h i+r 21, 1988, GA subnitted a report sunnarizing the final surveys cenpleted for " Group 3" laboratories (Reference 1). Subsequently, o

GA also decontaminated Laboratory 315 and Rocns 1 and 2 in Tahnratory 309.

Preltninary surveys were provided to the Nuclear' Regulatory Commission (NRC) on February 28, 1989 sunmarizing the decontamination efforts. 'Ihese prelimina q surveys are also provided in this report. At

• hmant 1 is the survey of Laboratory 315 and Attachment 2 is the survey of Rooms 1 and 2 of Laboratory 309. Note: Room 3 of Laboratory 309, Laboratory 307 and Roan 311A (surveys conducted in roan 311A in 1977 show some residual contamination which may require decontamination) will be decontaminated at 4

a later date.

Under contract with the NRC, Oak Ridge Associated Universities (ORAU) mnav ted a confirmatory survey of the " Group 3" laboratories and the Stage 2 area of Building 9 during the period March 14-24, 1989. ORAU included Imb 315 and Rocas 1 and 2 of Iab 309 in their confirmatory survey. A final report documenting these surveys was empleted in July 1989 (Reference 2).

'Ibe labs have been released to unrestricted use.

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1his wi. fewun11y rkn=ar*= GA's surveys of lab 315 and noms 1 and -

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2 of Iab 309 and ptwides infoonst3m on soil sample results after e b==

of Roans 1 and 2 af Imb 309.

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% e total area of lab 315 is 288 ft and the total area of rooms 1 and 2

2 2 of lab 307/309 is 620 ft ; for a total of 908 ft,

I A brief history of the use of these laboratories is provided, ne t

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primary radionuclides previously used in these laboratories were Cs-137, j

Sr-90, and other. fission products, Co-60 and other activation products,- as l

well as uranium (including various enrichments of U-235) and thorium.

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Both of these laboretories required decontamination. The primary ocnuminants found during the decontamination efforts were Cs-137, Co-60 and Sr-90. Lab 315 had several small areas which required decontamination I

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(~ 1 ft ).

%ese areas were decontaminated'to levels below the guideline limits. %e decontamination efforts in roans 1 and 2 of lab 209 involved retoval of the drain pipe (c+a+1 off after ratoval of an underground tank in 1984), retoval of contaminated concrete fran the floor and walls (until residual contamination was below the guidelines) and removal of ~375 ft3 of contaminated soil, drain pipes and concrete. Soil was removed until the.

h residual met the criteria approved by the'U.~S. Nuclear Regulatory Carmission (NRC) and endorsed by the Department of Health Services for >

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application at GA's site. %ese criteria for releasing soil to unrestricted use are summarized in Tables 2 and 3 (AtC--MLs 6C and 6D).

l Soil sattples (including catposite sanples) were taken in every exposed location after clean up in order to demonstrate coupliance with the soil criteria.

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GA has decontaminated these' laboratories consistent with the State of California's and U. S. Nuclear Regulatory Catmission's gn4Mimaa for Release of Facilities and Equiptent to-Unrestricted Use. The results of the final ~ radiation and contamination surveys are included in this report to demonstrate catpliance with the guidelines. The results of the-analyses of soil sanples (collected after cleanup) are also included in this report to demonstrate canpliance with the soil target criteria.

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a SI'IE DESCRIPTICH I

The location of Building 2 with. respect to other facilities on the GA l

Site is shown in Att e hmant 3.

A layout of Building 2 is shown in Atte hmant 4.

The building is divided into three Iaboratory sections; Iaboratory B, C, and A.

Laboratory B includes offices and laboratories fran 102 through 243.- Laboratory C includes offices and laboratories from 300 through 445 and Laboratory A includes offices and laboratories fran 502 through 651. The laboratories to be released to unrestricted use (Imb 315 and Roans 1 and 2 of Lab 309) in "A+hinm to Group 3" are located in the Laboratory C section (see Attachment 5).

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l Labe 307 and 309 were carbined labs consisting of four (4) rooms (See I

Attehmant 2) which were frequently referred to as one laboratory, namely Laboratory 307.

In this report rooms 1, 2 and 3 are referred to as Lab 309-roans 1, 2 and 3 and roan 4 is Lab 307 (See Attehmants 5 and 8). Both l

labe 307 and 309-had drain lines connected to an urdru f.vand storage tank located outside of the building which was usually referred to as the "L 307 tank". The "L 307 tank" and surrounding contaminated soil were renoved da 1984. The drain line fran the tank to Labe 307-and 309 were emwi off s

(see At+ehmant 8) when the tank was renoved. A report h= anting this effort was subnitted to the NRC on Noveuber 30, 1984 (Reference 3) along with a request to back fill the hole resulting fran the removal of the -

tank.

Laboratories 307/309 had been cleaned (including sandblasting) i initially in ~1978. Subsequent radiation levels were greatly r=+M but did not meet the limits for release to unrestricted use. In February 1989, the drain line to the laboratory was removed and decontamination efforts to release labe 307 and 309 to unrestricted use began. Iabs 307 and 309 2

occupy an area of approximately 1150 ft.

In addition, Roan 311A (~100 2

ft ) which was also used during the same time frame may also have to be decontaminated at a later date. This report covers roans 1 and 2 of lab 2

309 having an area of about 620 ft. The rest of the area consists of room 3 of lab 309, room lab 307, and room 311A which have a total area of about 2

630 (including the 100 ft area of room 311A).

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TARGET CRIIERIA FOR REIEASE E UNRESTRIC'IED USE Se following crite ria have been approved b(. the NRC and the State of California for the GA site.

i FACILITY AND EQUIPMEtc Table I (Attachment 6A) is taken from USNRC's criteria for releasing i

facilities and equipannt to unrestric^M use. It has been incorporated into our StW-696 license. Se State of calHornia's limits for release of facilities and equipnent to unrestricted use are identical to these limits for the radionuclides of concern (p-d-winantly Cs-137, Sr-90 and Co-60).

Sese guidelines, "DHS Criteria for Release of Facilities and Equipnent to-Unrestricted Use," are also known as "DE00N-1" are sumnarized in Table I (Attachment 68). GA has decontaminated the laboratories to levels below these guide 14nm.

SOIL CRTIERIA n e criteria for soil decontamination is given in Tables 2 and 3 (Attehmants 6C arn 6D, respectively). These criteria have been previously approved by the NRC for use at the GA site and were approved by the Department of Health Services. Table 3 (At C - i. 6D) provides soil concentrations in pci/g which if residing on the surface and inhaled would not lead to an expoeure W ing the target critaria in Table 2 (Attehmant 6C).

Soil exposed during and after remwal of the drain pipes in lab 309 was analyzed by gamma sgLwscopy to deramina the various radionuclides and radioactive concentrations of each. Mta: chemistry was also performed on selected soil sanples to determine the Sr-90 soil concentrAt. ions. If the levels were above the soil criteria sumnarized in Table 3 (Attehmant 6D),

soil was renoved until these levels were met.

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e-1 INSTRlHENTATICE AND MEASURfNENT LIMITS POR RELEASE Instrumentation 1.

Seta/gama counters - Model ' IBM-28 and Model TBM-15 gelger counters manufactured by Technical Associates were used to survey surfaces for beta / game contamination. 'Ihe instruments contain a pana=1ra Geiger-Mueller (CM) detector which has a window thir4rnans of less than

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7 ng/cm. h instrument has three ranges covering frun 0-50,000 counts per minute (cpn). 'Ihe instruments are calibrated asunianntially using a Cs-137 standard or a pulser.

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Ganma Detectors - Model 19 microR meters with NaI scintillation detectors nanufactured by Ludlum Heasurements Inc.- were used in all locations. The instrument has three ranges fran 0 - 5 nR/hr. 'Ihe microR meters are normally returned to.the manufacturer for m1ibration annually. Gamna spectral analysis on selected sanples were performed using a high purity gamanium detector manufactured by Canberra Industries, Inc.

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Iow level, Alpha / Beta counting systens manufacttred by Canberra were used to analyze wipe sanples.

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h alpha / beta systems and the gamanium detector systen has been calibrated for various types of sanples..This calibration is checked on a daily or weekly basis riapaneling on usage.

Measurement Limits Jg Release The final survey resalts have been converted fran cpu (counts per minute) 2 for a particular detet. tor to dpn/100 an. Detector "bechy.vand" cpn are subtracted fran measure.' readings. The values are then corrected for efficiency and geceidric factors associated with the instrumentation.

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Backcround A " standard" natural background was determined for each instrument and 5

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4 subtracted fr a the survey readings. '1he surface beta /gama readings were ceripleted using the TBM Hodel 28 and ledel 15 Q4 counters which have a background concrete reading of about 80 plus or minus 20 counts j

per minute.

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Efficiency NBS traceable standards were used to calibrate in.ia.m ids for various efficiencies. The standards consist of concrete blocks (one for each radionuclide)- having an area of approximately 25 m x 25 m spiked -

with an NBS traceable standard liquid solution of the specific radionuclide i.e. cs-137, 93% enriched uranium, depleted uranium and thorium. '1he maxinun ' allowable level is 15,000 dpn for an area less 2

than 100 cm and the average allowable level for an area 1 meter by 1 meter or less is 5000 dpn/100 m2 (At+ehmants 6A and 6B). Surface' measurements of the blocks were obtained with the' instruments and-percent efficiencies were obtained. The rauwHnga were cw.i ct.ed for efficiency by nultiplying by the appropriate correction factor.

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GecH-Lry Correction 2

l h acceptable values listed in Table 1 are in dpn/100 m, therefore,

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a correction factor was applied to the measured values to correct for the smaller area of the detector, h Model ' IBM-28 and Model TE4-15 (geiger counters) have a 5 m diameter detector which measures a 19.6 2

'1he reading is therefore corrected by nultiplying by 5.1.

m area.

The alpha detectors used for the surveys "see", at any given time, an

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2 area of about 78.7 m, which then requires a correction factor of 1.27.

l PREVIOUS LABORMORY ACTIVITIES A brief description of the previous use of these laboratories over the past approodmately 20 years is provided below.

Information is also provided below on the work involved in cleaning these labs and the'results of initial surveys of these laboratories.

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' 4-.6v 315 (No enina) i Previous History In the early 1970's, various experinents involving the use of fission

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products as tracers for kinetic and therno$namic properties of high 1

tenparature materials were conducted in these laboratories.

In addition, 1

Cs-137, I-131, Ag-110 and N 127 were used for namal adsorbtion studies j

(W rk Authorizations #2000, 2059, and 2073).

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1989 Decontamination Effort surveys using geiger counters and microR meters showed no contamination on the floor (tiled) or walls of the laboratory.

several small areas were identified by ORAU as namiing additional cleanup (below tile floor and wall) during the confirmatory survey empleted March 14-24, 1989. ORAU re-surveyed the areas after GA decontaminated them and found the levels to be below the release criteria (Reference 2).

_Romas,1, and 2., of Tahrratory 309 (No Mammnim)

Previous History

'Ibe Work Authorization records seemed to refer to these two laboratories as Lab 307. For this reason, all W rk Authorizations referring to-" lab 307" are assumed to be for lab 309 also.

W rk Authorization #1459 was approved in August 1969 to allow the possession of 50 grams of depleted uranium for " parting ' discs of UC with 2

a diamond wire saw".

In 1970, the possession limit was increased to 300 grams U-238.

trk continued until ~4/77 in these labs under several different Erk Authorizations. -NU s #1882 and #1967, approved 8/15/72, authorized the cutting of Peach Bottan spine elements to begin diffusion experiments.

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1. 1983, approved 10/1/73, covered all fuel chemistry branch work requiring 7

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'Special Nuclear Material (SW) and other radioactive naterials. m #2021, issued 4/24/74, allowed both SM and non-SNK to be used for ch-kal and instrumental analyses on naterials. E 's #1907 and 2023, approved ~5/73, authorized mixud fission products and U-235 to perform post irradiation l

analysis of irradiated-fuels (Uo ' UO /Tho ' UU ) f vari us U-235 2

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enrichments. m 62029 was issued to conduct analysis of Peach Botta fuel j'

elenents and HMR core materials. E #2033, approved 8/29/74, to irradiate Uo in Pellet form in stainless steel cans and eranine segnants 2

-of fuel cladding and structural conponents for fission gas and tritium l

l analysis at 'JRIGA and Hot Cell. R #2061 authorized autoradisp. @ y of irradiated fuel bodies and m's #2051, #2091, and #2166 authorized miscellaneous mcwurements of spei=nm (irradiated carbon, silicon carbide, etc.) until 4/15/77.

The records do not show any other m's issued for these laboratories beyond 4/15/77.

1977 Decontamination Effort In 1977, decontamination of the laboratories began (information was obtained fra Health Physics Log Book #7467). Rooms 1 ard 2 were I

i decontaminated (including sandblasting) fr a relatively high radiation levels to low radiation levels. The roms were coupletely enptied, room 2 l-was retiled, the drains were plugged (see with lead and cement

" patches"), and the drain linos were tagged with " Caution Radioactive Materials" labels. 'Ihe labels on the drain lines identified the Health i

Physics log book which documented this effort. The radiation levels after c

the roms were cleaned constitute the " Initial survey".. Some of this information is presented in Attachment 9.

d 1989 Decontamination Effort c

2 In rom 1 (~350 ft ), the concrete floor areas represent about 318 ft ;

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the rest of the floor area (about 32 ft ) are soil trenches resulting fr a the renoval of the underground drain pipes. CRAU identified an area of the floor along the southeast wall which needed additional clannup.

GA retoved a segnent of concrete and disposed of it as r=41rw;tive waste.

9+8w31ent surveys by the ORAU team showed levels were below the

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guidelines.

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'In room 2 (~270 ft ), the new tile. installed after the original cleanup in-1977 was removed. We concrete was also coupletely retoved fra the floor surface, ne underground drain pipes were then removed. The highest i

radiation level noted on the pipes was ~8 mR/ hour beta /gama. Trenches l

were formed by the restoval of the pipe shown as the dotted areas b At+r 1-M.s 10-13. Contaminated soil was detected using microR meters and geiger counters. S e drain pipes and the soil below the drain pipes were reoved and dia:-d of as radir=2.ive weste.

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surface soll sanples were collected from each area exposed. Sanples were dried to retove noisture and then analyzed by gama ray sps.hv&,vyy using 1

a high purity gamanium detector system in accordance with written e vcodures. All gama emitting radionuclides were identified and their concentrations were deraminad, he 2-232 value was obtained based on' s

the concentrations of the daughter radionuclides. Th-232 was assumed to be in equilibrium with its daughters. Het chemistry was also performed on selected soil sanples to determine the Sr-90 soil concentrations. Results I

of the soil sanples showed predominantly Cs-137, Co-60 and Sr-90 contamination (the pipe had rusted through resulting in soil contamination).- The locations of the initial soil sanples are provided in

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At+e hmant 10 and Att e hmant 11 provides the results. A few of these locations had soil contaminated to levels which excaadad the release criteria described in Tables 2 and 3 (Attehmants 6C and 6D, respectively). In these areas, soil was renoved until the approved levels were met.

Final soil sanples were collected in all areas where-additional cleanup was conducted. Individual soil sanples as well as conposite soil sanples were collected. %e locations of the sanples are shown in At+ehmants 12

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and 13. The results of these sanples are shown in Attehmant 14. No additional soil sanples were collected in those areas where the initial soil sanple result did not exceed the soil release criteria. A total of ~

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375 ft of soil was removed during the cleanup stage _ representing about fifty (50).55 gallon drums of contaminated soil; three of the 55 gallon 3

drums of soil (~22 ft ) were reroved during ORAU's visit after analysis of l

a sanple collected in the " pit intersection" (see Attachment 12 for 9

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4 iocation) by ORAU and split with GA showed some Co-60. Although I

the levels would have met the guidelines (because it is an area less than 30' by 30'), additional soil was renoved to reduce the levels (see j.

Att ehmant 14 for results). Subsequent samples collected in this area by l-CRAU and split with GA were also analyzed l_Wiately in the Health

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Physics Laboratory. These results (Attehmant 14) showed contanination l

levels were well below the target, criteria provided in Table 3 (Attehmant j

6D). All other sanples split with the ORAU durlag their visit were also analyzed and found to be well within the target criteria.

l K. 2ng representing the State of California also collected soil sanples in the " pit intersection" area subsequent to the above described removal of acklitional soil. _ 'Ibese sanples were also split with GA. GA counted the sanples in the Health Physics Iaboratory. The results (provided in Attehmant 14) showed levels were below the soil criteria concentrations for release to unrestricted use.

1 During ORAU's survey of this rocxt., sane spots were found on the walls.

'Ihese spots were decontaminated inmediately and re-surveyed by ORAU.

Izvels after additional decontamination were below the guidelines for release to unrestricted use (Reference 2).

FINAL RADIATION SURVEYS i

i Final surveys of Lab 315 and Rooms 1' and 2 of lab 309 were conducted using the Model ' IBM-28 and Model TBM-15 gelger counters. The measurements of average contamination were averaged over 1 meter 2 and are given in 2

c% n/100 cm. The mav4=nn contamination level applies to an area of not 2

more than 100 cm. Atte hmant 7 provides the final survey of lab 315.

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Roans 1 and 2 of lab 309 were surveyed primarily.during the ORAU visit. Areas requiring additional cleanup as identified by CRAU were decontaminated by GA personnel. Ievels after acklitional decontamination

- were below the guidelines for release to unrestricted use (Reference 2).

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A microR meter was also used to survey the laboratories and to measure floor radiation levels. Radiation levels in Lab 315 were at normal background levels (see Attachment 7)'.

Radiation levels on the soil surfaces in Roams 1 and 2 of Iab 309 were less than 30 microR/ hour after remwal of the contaminated soil. Ievels below this indicate that soil-radionuclide concentrations for the radionuclides of concern are below the a

soil target criteria.

FINAL CmTAMINATION SURVETS

-y Table 1 (Attachments 6A and 6B) provides limits for acceptable removable surface contamination levels. Contamination surveys (wipes) were conducted although no renovable contamination was suspected i.e. the labs had not been used for several years. The wipes were collected on the floors of Iab 315. The wipe sanple locations are shown in Attachments 7 and the results are shown in Attachment 15.

The contamination levels in every location were ( 20 dpn/100 cm2 area, and well below the Table 1 limits (Attachments SA and 6B) for removable contamination.

03PLIANCF WIN WE TARGET CRIERIA Facilities and Equipnent

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All floors, walls and concrete. surfaces were decontaminated below.the release levels specified in Table 1 (At w hmant 6A and 6B). The final surveys provided in this report denenstrate ccupliance with the criteria for release to unrestricted use.

Direct Radiation i

The direct radiation level at all areas of Lab 315 and Roans 1 and 2 of Iab 309 are less than 10 microR/hr above background (at one neter above ground level). All surface radiation levels on the soil inside the a

trenches was less than 30 mircoR/ hour after removal of the contaminated soil.

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e Soil Limits.

h results of soil sanples collected in every area after cleanup show levels are well below the target criteria specified in Table 2 and 3 (Attachments 6C and 6D).

CCNCLUSIG4 Final surveys of Iab 315 and Roma 1 and 2 of Imb 309 and results of ~ final soll sanples collected in Rocns 1 and 2 of Lab 309 provided in this report.

deonstrate that the levels meet the guidelines for release to 4

unrestricted use.

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Asmussen, K.

E., letter. 9696-1318 to Mr. Robert D. Thcanas,

" Request for Release of Selected Laboratories to Unrestricted Use (Group 3)", dated C+;--J_+r 21, 1988.

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Yuhas, G.

P., letter dated August 18, 1989 to Mr.'R. N.

Rademacher, "NRC Inspection", with ORAU Report i89/F-98 identified as NRC Inspection Report No.- 70-734/89-02.-

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Mawry, W. R., letter f.696-6083 to Mr. W. T. Crow, " Request for Approval to Backfill L-307 Pit", with report entitled " Final Report L-307 Pit at GA site" dated Novenbar 30, 1984.

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ATTACHMENT'1 FINAL 80RVEY OF LAB 315-1 l

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FINAL SORVEY COMPLETED 2-28-89 Instruments used were:. Ludlum 19 microR= meter #33545 j

calibrated 11-11-88,. and geiger counter TBM-28 #108113 l

calibrated 10-31-88.

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Each unit. represents a three foot by three foot area or less.

et 2.

Top value is the average-beta / gamma contamination in DPM/100 cm square 1

f in a three foot-by three foot" area or less.

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Bottom value is the= maximum beta / gamma contamination in DPM for an area'<100 cm. square.

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Circled numbers are wipe: locations.

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Numbers in squares.are measured'microR/hr. levels.

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No contamination requiring cleanup was detected in this lab.

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ATTACHMENT 2 Page 1 of 2 Draft Sursnaty i

2/27/89 i

asumary of the h hia" of i

IABB 307/309 for release to unrsstricted use i

l Labs 307/309 are located in the Laboratory B section of Canaral h*=le's pii Mie 2.

These labs had dra h lines connected to an ursky.vand tank' called the *L-307 tank". This tank and sun-M47 j

contaminated soil were remwed in 1984. Se drain line fran the tank 3

to Lab 307/309 was capped off when the tank was renoved.

i During the past few months, the drab line to the laboratory was runwed and decontamination efforts to release labs 307/309 to l

l unrestricted use begpn.

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.hese efforts are beirq ccupleted in two parts. Se in the attachment) occupy an area of.yy.w.1:stely 1150 ft} abs (shwa j

Part 1 consists of two roczas (rocus 1 and 2) having an area of about 620 ft.

2 Part II (rocy 3 and 4) also consists of two rocras and has an area of l

about 530 ft.

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We have finished decontamination of Part I and would like a confimatory survey empleted so we can returhish the area.

Additional infornation is pewidad below:

i The ura,.vand drain pipe was renoved in el of the Part I arman l

shcun in the a++= hM drawing. A trench was fonned by the renoval of the pipe shown as the dotted areas b the drawing.

Soil sangles collected inside the rooms showed same soil cort-inef an below the l

pipe (indications are that the pipe had rusted resulting in same soil l

contamination). Se p. hhnt radionuclides found in the soil were Cs-137, Co-60 and Sr-90. Forty-four drums (55 gallon) of soil were ru oved from the L..rslwks. Ennfim= tory sod sanples collected after renoval of the soil were analyzed. Concentration valt2% for both l

Cs-137 and Co-60 were found to be well below the criteria prwiously al. proved by WC. We are awaiting final soil sanple results for Sr-90 and are expecting the values to be ( 100 pCi/ gram. This is because saples coun:ted before cleanup was ccmpleted were analyzed to have (

i 300 pCi/grare.

Since the limit for Sr-90 is 1800 pCi/ gram (Option 1 critaria Unit for innalation doze, we should meet the criteria, ne surface radiation levels are (10 above background at one meter.

2 Inroom1(~350ft),theconcregefloorareaswhichu:midneed f

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(about 32 ft are teoil trenches). In rocan 2 (~270 ft, the concrete i

was removed ccmpleted from the floor surface so the area is exposed to soil. The soil trenches in the rocan are shown in the i

drawing.

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l ATTACHMENT 6A 1

TABLE 1 ACCEPTABLE SURFACE CONTARINATION LEVELS I

WUCLIDES*

AVERAGEbcf RAMINUNbdf EfEMPWABLgb e f i

l U-nat U-235, U-238 and cssociated decay products 5,000 d p e/100 cm2 15,000 dpm e/100 cm2 1,000 dra e/100 ce2 Transuranics Es-226 Ba-228, i

Th-230. Th-2E8, Pa-251, Ac-227, 1-125, 1-129 100 dyn/100 cm2 300 dyn/100 cm2 20 dpm/100 cm2 Th-nat, Th-232, Sc-90 Ca-223, Ra-224, U-232, I-126 1-131, 1-133 1000 dyn/100 cm2 3000 spe/100 cm2 200 dyn/100 cm2 Beta-samme emitters (nuclides with decay modes other than olpha emission or spontaneous fission) except Sc-90 and i

cthers noted above.

5000 dpm Sy/100 cm2 15,000 dre Sy/100 cm2 1000 dpm Sy/100 ce2 i

• Where surface contamination by both alpha-and beta-gaaume-emitting nuclides exists, the limits established for c1pha-and beta-gasem-emitting nuclides should apply inde;-- M.tly, bAs used in this table dpm (disintegrations per minute) means the rate of emission by radioactive material as determined by correct ['ng the counts per minute observed by an appropriate detector for background, efficiency, and geometric factors associated with the instrumentation.

C Nessurements of average contaminant should not be averaged over more then 1 square meter. For objects of less surface area, the average should be derived'for each such object.

dThe maximum contaminatior. level app 11es to'an area of not more then 100 cm,

2

'The amount of removable radioactive material per 100 cm2 of surface aree should be determined by wiping that crea with dry filter or soft absorbent paper, applying moderate precouro, and assessing the amount of radioactive material on the wipe with an appropriate instrument of known officiency. When removable

,~

coritamination on objects of less surface area ls s'etermined, the pertinent levels should be reduced i

proportionally and the entire surface should be wkped.

IThe average and maximum radietion levels associated with surface contamination resulting from beta-gasuna emitters should not exceed 0.2 mead /hr at I cm and 1.0 stad/hr at I cm, respectively, measured through not more than 7 milligrams per square centimeter of total absorber.

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• MAXIM.lfd EMNABLE

• 6 2

(dpm/100 cm )

(dpm/100 cm )

(dpm/100 c=2) la) U-nat, U-235, U-238, and 5,000-15,000 1,000 I

c0 ociated decay products

b) Tr:nsuranics, Ra-226, Ra-228, 100 300 20 2-230 Th-228, Pa-231 r

A3-227, f-m, I-124

.'c) 2 -nat, n -232, Sc-90 1,000 3,000 200 Ra-223 Ra-224, U-232, I-126 I-131. I-133 s

d) Dats-gamma emitters (nuclides 5,000 15,000 1,000 with decay modes other than alpha emission or spontaneous fission) except Sr-90 and Cthers noted above.

o) H-3, C-14 except as DNA 20,000 60,000 4,000 pr: cursors ff

.'Whora surface concaminacion by both alpha-and beca-gamma-emitting nuclides exiscs, che limics ss ccblished !ct alpha-and beca-ga..~na-emitcing nuclides should apply independencly.

3A.s uced in this table, dpm (disinceptacions per minute) m'enns che race of emission by radicaccr

..scarial as determined by correccing the councs per minuce cbserved by an approprince dececcc:

fcr bcckground, ef!!clency, and geomectic faccces associaced wl.h che inscrunencacicn.

'M3 curements of average concaminanc should not be averaged over more than i square.mecer.

Tcr cbfcccs of less surface ares, che average shculd be derived !ct each such cblec:.

iho maximum concaminacion level applies cc an area of not more than 100 cm.

'Tho amounc of removable radicaccive macerial per 100 cm# of surface area should be decermined cy wiping chac area with dry !!1ter or soft absorbent paper, appiving mderace ' pres 3U:** and ascocaing the amunc of radioaccive macarlal on the wiye with an appropriace inscrument of know o!!iciency.

When temvable concaminacion on objects of less surface area is decermined, the percin:nc levels should be reduced proporciona11y and the entire surface should be wiped.

' 'D.*.*A pr: cursors mean molecules. or compounds that are directly incorporated into the DNA wiecule.

during DNA biosychesis, e.g. purine and pyrimidine bases and their analogs, nucleotides and n ucle'osides.

The accepcable surface contamination levels for N-] and C-14 in DNA precursors

{

ago cc tabulated in paragraph (d) for beca gamma-emitters.

i h USNRC Regulacory Guide 1.86 Terminacion of Operatina Licenses for Nuclear Reactors, Washingto?.

D.C.

( Une 1974)

.'/ ANSI, Control of Radioaccive Surface Concamination on Materials, cauloment and Facilities

~

To 84 Released for Uncontrolled Use. final draft, Droposed Americart Nacional Standard N-328, Atomic Industrial Forum, Inc., N.Y.

(June 1974)

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ATTACHMENT 6C TABLZ 2

(

Criteria for Soil Deccatamination at the G1 g i

i Exposure Target other Existing I

Pathway Critaria Criteria or Guidance External Radiation 10 ur/hr 20 gr/hr indoor DA cleanup (wncle body)

(35 e==/yr)(,)

standard for Inactive uranium

-l Processing Site; 500 ares /yr-10 CTR 20; 170 rem /yr4RC Guidance; 400 900 ares /yr-4ur-geen General's Guidance for in-door exposuret 25 res/yr-40 CTR 190.

Inhalation of Partte-1 arad/yr (1 ulates (lung, bone)

(20 run/yr)gg) 1500 mrea/yr-10 CTR 20(d

25 area /yr-40 CTR 190

- t 3 mrad /yr (bone)-

1 mrad /yr (lur.g), 3 mrad (bone) l (60 mrea/yr)

EPA 3 ansuranic Guidance i

l-o (a)This value does not include background

, the 35 ares /yr (realistic dese) includes shielding factor of 0 5 fetus building a residential l

home for general population and residence time 80 percent.

(b)40 CTR Part 192 - Federal Register 1

, April 22. 1980.

l (c) Based on quality factor of 20 as origdn=1ly intended for al h emitted from the transuranic elementa.

pa i

Designated in or derived from l'O CTR 20.

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ii ATTACEMENT 6D

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TABLE 3 l

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Individual Concentration in Soil Resulting ih an Annual Inhalation l

III Dese of 20 mese to the_Lgu and 60 meen to the BoneI23 I

Solubility Derived Concentration (DCi/t) 1.

Radionuelide Classi fication Luna (20 meem/vr)

Bone (60 mrem /ve)

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35 2.6 x 10 2

2 Th432 W

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3 l

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3 l'

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4 4

6 Co-60 Y

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6 Co-40 W

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9.6 x 10 3,3, 3n 5

6 1.8 x 10f '

2.6 x 10f Sr-90 Y

Sr-90 D

1.6 x 10 2.8 x 10 (1) Pulmonary lung (570 ga); consistent with EPA 's Transuranic Guidance.

(2)

Bone means osseous tissue (5,000 ga); consistent with EPA's Transuranic Guid ance.

(3) The daughters of Th-228 and Ac-228 do not contribute significantly to the j

inhalation dose because of their comparatively short half-lives..

(4) Solubility classifications are based on ICRP-30 1-i t

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Notest

1. Final s empleted February 28, 1989 using gel r counter '196-28

1. 108113 cal ated October 31, 1988 and Model 19 meter #33545, calibrated Novenbar 11, 1988.

2. Each unit represents a three foot by three foot area or less.

2

3. 'Ibp value is the average beta /gama contamination in DPM/100 an in a three foot by three foot area or less.

4. Bottaa value is p mL=wn beta /gama contamination in DPM for an area less than 100 on,

i

5. Circled nunbers are wipe locations.

l

6. Numbers in squares are measured microR/hr radiation levels.

7. During the ORAD survey, same contamination was detected on several-l smgliareasofthefloorandwall. The arrall areas (a total of about 1 ft in area) were decontaminated to background levels.

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Initial survey completed 10/77 (Log Book #7467).

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2.

Values are counts per minute (cpm) beta / gamma radiation levels using a geiger counter.

3.

Room 2 was re-tiled after initial decontamination in 1977.

Clean tile was removed in 1989.

Concrete, drain pipes and contaminated soil were removed in 1989.

4.

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M 10 10 0.20 _+ 0.06 10 1.# _+ 0.30 0.90_+ 0.30 1.30_+ 0.20 1.00_+ OAO 0.11.+ 0.03 N

10 DD 10 10 1.40 _+ 0.10 0.~10 _+ O m 1.30_+ 0.30 2.0_+ 0.30 0.32.+ 0.02 O

0.5010.01 le 0.810.02 10 0.9010.03 0.60 1 O R 0.90 + 0 2 1.3 + 0.30 0.09 1 0.01 s

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anrurE REL SWEG5g JEBUBIEE 13 RR EDItDE) j n_

u-1 0.50_+ 02 0.06.+ 0.2 2.20 _+ O R 10 1.30_+ 0.07 0.90.+ 0.07 1.30_+ 0.30 1.80_+ 0.30 0.17.+ 0.03 7

j n-u-2 0.6010.03 0.3010.03 3.@ i 0.04 0.1810.06 1A010.06 0.9010.0B 1.5010.08 2.310.M 0.0910.04 5

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o.asio.01 10 o.9sio.m o.152o.os 1.os2o.m 1.7310.12 o.141o.01 comnea7 m

!O 1.201o.os m

1.e i o.12 1.caio.n 1.75io.as 2.ssio.as o.231c.e aussoossosos m

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i ggg.g',g, CROSS ALPHA / BETA COUNTIND RCSULTS FOR WIPE SAMPLES ALPHA DETA COUNT SAMPLE ID LENGTH DPM/100 SQ.CM.

% ERROR Df'M/100 SR.CM.

% ERROR MIN 95% CL 95% CL j

L-315 W-1 Lab 3151.

(9.740E-03 95.00 4.770E 00 50.97 l

1 0 3/16/89 Lab 315 1.

<9.740E-03 75.00

<4.66CE-01 95.00 j

3 Lab 315 1.

<9 740E-03 95.00

<2.905E-02 95.00 4

1.

<9.740E-03 75.00 (1.000C 00 95.00 Lab 315 AVERADE 9.740E-03 1.568E 00 l

HIGH 9.740E-03 4 770E 00 LOW 9.740E-03 2.905E-02 NOTE! THE ERRORS DO NOT INCLUDE INitCRENT EFFICIENCY CALIBRATION UNCERTAINTIES.

i Notot See Attachment 7 for wipe sample locations 4

I I

' 5:

Contamination Survey Results i

l t

I

pr.

. j.

A e e/ T.

n e

s DIFECT Dilri CITJATIGJ.>

Did tiu AESTS14JT STATIDs D4IFT EU ETMIER:

(a) Tate TI!CLY. LEUISILE /CTILtJ w'.v. reobicac e.rctc?

3 2

1 ~

Tcok early rwcdial Miror inctances of Failure'to take recuperative acticn failing to take tinely acticn when necessary.

acticn within resulted in reasonable goried of deterioraticn of

tine, plant ccnditions.

(b) Prodde TItCLY, WELL T}0LG47 DJT FECDtEICATIDE OR DifECTICtG that facilitated crew perfonnance and dcocnstrated appropriate ccncern for the safety of tre plant, staff, and public?

3 2

i Rccomendaticns Minor instances of Reconnendations and or directives incorrect, trivial directions inhibited enabled safe, cr difficult to performance; crew had integrated crew carry cut aciens.

to explain why action ptrformance.

couldn't or shculdn't te follcwed.

(.,

(c) Stay in a position of OvERSITE providing an appropriate amount of

~

Direction and Guidance?

3 2

1 Stayed involved, but.

Crew had to solicit.

Lost the big

' without teing tco assistance on picture; SSS had to intrusim; cccasicn, interfering repeatedly regtest anticipated crew with t.'eir ability to assistance; failed needs and provided carry out acticns.

to verify correct guidahcb when enactnent of SSS necessary.

directi ms.

(d) SOLICIT tEd IllTrftTATE FEEDNm from crew to 1ceter an ' effective, team orientated approach to prob 1cm rolving/decisicn making?

3 i2

.1

,..,f.7in 4

Irwolved crvw in

' ; Atitimcs,I1 ailed to Decisions nede I

problem solving

.,. ' fir @o1Veicrew in:

wittcut needed crew prccess as l

y}(.d[decisionf making wtcn particip&ticn or appropriate, leading; itjwould. have tecw censultation; crcw to of1c<tive team *

appropr16te,'

divisiveness was

' decisicn making.;

4 3 4'"idetracting;from team counter-prcductive.

"orientatrd approach.

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