Text

Decontamination of Hot Suite Area of Triga Fuel Fabrication Facility Formerly Located in Bldg 9 for Release to Unrestricted Use Stage 2
	ML20248C442
Person / Time
Site:	07000734
Issue date:	08/31/1989
From:	; GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:	;
Shared Package
ML20248C440	List: ML20248C435; ML20248C442;
References
	NUDOCS 8910030467
	Download: ML20248C442 (29)
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' DECONTAMINATION OF THE

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" HOT SUITE" AREA 0F THE TRIGA FUEL FABRICATION FACILITY FORMERLY LOCATED IN BUILDING 9 FOR RELEASE TO UNRESTRICTED USE j

STAGE 2, e

AUGUST 31, 1989 b

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TABLE _O_F CONTENTS

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LIST OF ATTACHMENTS.......................................i INTRODUCTION............................................. 1 SITE DESCRIPTION..........................................

3 HISTORICAL OVERVIEW OF PROCESSING ACTIVITIES..............

6 TARGET CRITERIA FOR RELEASE TO UNRESTRICTED USE...........

6 RADIATION DETECTION EQUIPMENT.............................

6 INITIAL SURVEY AND DECONTAMINATION METHODS................

9 FINAL RADIATION SURVEYS..................................

10 FINAL CONTAMINATION SURVEYS..............................

11 COMPLIANCE WITH THE TARGET CRITERIA......................

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CONCLUSION...............................................

11 REFERENCES...............................................

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LIST OF ATTACHMENTS Attachment la Plan View of Site :

First Floor Experimental Building showing the Previous Location of the " Hot suite area a :

Current Configuration of Former " Hot Suite" Area :

View Graph Showing the former " Hot Suite" Area (overlap with Attachment 3)

) :

Decontamination Stages for the " Hot Suite" area A Table I Guidelines for Release of Equipment and Facilities to Unrestricted Use (NRC) B:

Table I Guidelines for Release of Equipment and Facilities to Unrestricted Use (State of California) :

Initial Survey of Stage 2 Floor Areas :

Final Survey of Stage 2 Floor Areas :

Surveys of the " Hot Suite" Stage 2 Room Walls (includes Wall Contamination Survey Locations) 0:

Contamination Survey Locations and Micro R/hr Radiation Levels on Stage 2 Floor Areas 1:

Contamination Survey Results i

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0 INTRODUCTION Until April.1975, TRIGA Fuel Fabrication activities licensed by the USNRC were conducted in two-locations in General Atomics' Experimental Building-(Building 9).

One location was in the east side of the.former

" Pilot Plant"'(high bay) area of the-building and the other location was in the northwest corner of the building. This area in the northwest corner was then known~as the " Hot Suite" area (See Attachment 2).

TRIGA Fuel Fabrication activities were transferred in April 1975 to a new

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facility at GA (i.e. Building 22).

Decontamination of the " Hot Suite" area began in April and continued until around July.1975. The area was decontaminated for nonradioactive use but was not " officially" released by NRC to unrestricted use.

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~ Radioactive material was still being used in other areas of the building.

General Atomics (GA) has no plans for conducting future activities involving the use of radioactive materials in the Experimental Building.

Accordingly, over the last two years, GA has been involved in the process of' decontaminating and obtaining the release to unrestricted use of the Experimental Building (Building 9).

-Beginning in October 1986, GA decontaminated the Experimental Building; except for the " Hot Suite" area. GA submitted a report dated July 28, 1987 to'the NRC and to the State of California (Reference 1)

- requesting the release of this building to unrestricted use.

This report included the former " Pilot Plant" area where a portion of TRIGA Fuel Fabrication activities were conducted but did not include the " Hot Suite" 1

area which was occupied by GA's telecommunication group at that time.

After confirmatory surveys were completed and the building was found to meet the release criteria, the State of California released the building to unrestricted use (Amendment #87 of GA's Radioactive Materials License #0145-80, Reference 2).

The NRC also released the i

building to unrestricted use on October 1, 1988 (Reference 3) after completion of confirmatory surveys, with the exception of the small " Hot Suite" area where certain TRIGA Fuel Fabrication activities had been located.

Please note: not all portions of the area referred to here as the " Hot Suite" area involved the use of radioactive materials.

As mentioned above, GA has no plans for conducting any future activities involving radioactive materials in the " Hot Suite" area of the Experimental Building (or any other portion of the building) and would like to release the area to unrestricted use.

However, since it was not feasible to move the telecommunications equipment and activities all at the same time, GA is surveying and pursuing the release of the " Hot Suite" area in three (3) stages.

The total area of the " Hot Suite" area is con:arvatively estimated at 4036 ft2 Stage l'(2880 ft2) includes Rooms 39, 48, 49A, 50, 47A, a hallway area east and south of room 47A and the rooms which previously housed the former " Clean Machine Shop" area (these are: most of Room 38, a hallway area east of room 38, and rooms 34 and 35).

Stage 2 (587 ft2) includes rooms 40, 41, 42, 43 and 47.

Stage 3 is room 49 (569 ft2),

In late 1988 and January 1989, GA surveyed and decontaminated Stage 1 (2880 ft2) of the " Hot Suite" area for release to unrestricted use and documented their results in a report dated January 27, 1989 and submitted to the NRC and State of California (References 4 and 5, respectively).

Under a contract with NRC, Oak Ridge Associated Universities (ORAU) conducted a confirmatory survey of the Stage 1 area on March 14-23, 1989 (in conjunction with the " Group 3" laboratories of Building 2).

The results of the confirmatory survey demonstrated that the Stage 1 area did indeed meet the approved criteria for release to unrestricted use.

These results were documented in a report issued July 1989 (Reference 6).

j In 1989, GA surveyed and decontaminated Stage 2 of the " Hot Suite" area for release to unrestricted use.

This report sn=marizes the surveys completed for Stage 2.

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. The equipment-(primarily telecommunications equipment) from the Stage 2 area was transferred to the Stage 1 area. The carpet installed over the original concrete floor in the Stage 2 areas was removed and the concrete.below it was been surveyed for contamination. Some areas of the concrete floor were found to be slightly contaminated (up to-1200 counts per minute, primarily along the cracks on the concrete floor in each of the rooms). The only observed contaminant was uranium; U-235 enrichment varied from about three (3) percent to about ten (10) percent as determined by gamma scans of samples from the Stage 1 area. About nine (9)'ft2 of the 587 ft2 floor area required decontamination; which represents about 2% of the Stage 2 area.

The concrete wac decontaminated by scraping /scabbling the surface.

One small area on the west wall (adjacent to the floor) was found to be slightly contaminated (about 1000 counts per minute)'and was subsequently cleaned.

No contamination was detected on the any of the other walls.

GA has decontaminated the Stage 2 areas consistent with the State of California's and U. S. Nuclear Regulatory Commission's guidelines for Release of Facilities and Equipment to Unrestricted Use.

The results of the final radiation and contamination surveys are included in this report to demonstrate compliance with the guidelines.

SITE DESCRIPTION The location of the Experimental building (Building 9) with respect to other facilities on the GA Site is shown in Attachment 1.

A layout of the Building showing the " Hot Suite" area is shown in Attachment 2.

The entire building, including second floors and mezzanines is almost 59,648 ft2 Of this area, the former " Hot Suite" occupies less than 4,036 ft2, shows the current configuration of the rooms which now occupy the former " Hot Suite" area. Attachment 4A shows the " Hot Suite" area as it existed when TRIGA Fuel Fabrication activities were conducted there. Attachment 4 is a view graph of this drawing which can be overlaid 1

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V on the drawing showing the current configuration (Attachment 3).

A comparison of the two drawings reveals that some of the original walls of the " Hot Suite" area were removed during the reconstruction of the area and new walls were installed. 'Because of these differences, the area (ft2) is conservatively estimated to ensure that all previous " Hot Suite" areas are included in the final release surveys.

The former " Hot Suite" area contained a " Hydride Room" (currently Rooms 39 and 50), a " Hot Machine" shop (currently Rooms 49A, 49, 40, 47; and portions of 47A, 41, 42.and 43),.a " Hot Furnace" or " Melt Room" (currently Room 48), a " Change Room" (currently a portion of room 47A and a portion of the~ hallway east and south of room 47A) and a " Clean Machine Shop" (most of room 38, a portion of the hallway east of room 38, and rooms 34 and 35).

The total area of the " Hot Suite" (4,036 ft2) is being released in L

three stages. Attachment 5 shows the various rooms involved in each of the three (3) decontamination stages.

' Stage 1'(2,880 ft2) includes Rooms 39, 48, 49A, 50, 47A, a hallway east and south of room 47A, and the rooms which previously housed the j

" Clean Machine shop" (most of room 38, the hallway east of room 38 and rooms 34 and 35). Stage 1 has been released to unrestricted use.

Stage 2 (58'7 ft2) includes rooms 40, 41, 42, 43 and 47.

Stage 3 is room 49 (569 ft2),

Note: GA has recently changed the room numbers in the Stage 2 area.

Rooms 40, 41, 42, 43 and 47 are now referred to as rooms 40 and 41 since there are no walls between the other rooms.

However, to be consistent with the previous reports (References 4 and 5), the "old" rooms numbers are used in this report. New room numbers are provided to preclude any confusion in the future.

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,e 2 for each room to be released to The approximate area in ft unrestricted use is provided below as well as the " stage" it is in.-

2 Room Approximate area (ft_)

. Stage 1 Room 39 246

- Room 48 528 Room 49A 456.

Room 50 174' Room 47A 137 Hallway (east and south of room 47A) 330 Former " Clean Machine Shop" Area Room 38-182-Room 34-286

c Room 35 370 Hallway area east of room 38 171 o

Total. Stage 1 2,880 s

l Stage 2

Room 40 106 i

Room.41 81 Room 42 94 Room 43 94

' Room 47 212 Total Stage 2 587 Stage 3, Room 49 569 Total Stage 3 569 TOTAL (All Stages) 4,036 The surveys in this report are limited to the rooms identified ao Stage 2.

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v HISTORICAL OVERVIEW OF PROCESSING ACTIVITIES The Hot Suite's existence began in 1958 primarily for the research, development, and manufacturing of TRIGA fuel elements in accordance with NRC (previously AEC) licenses SNM-69 and SNM-696. This work involved l

primarily the use of 20% enriched uranium (U-235). A review of past Work Authorizations revealed that it was also used for small test runs of prototype and non-TRIGA reactor fuel using mostly depleted uranium.

In addition, a large batch of fuel was fabricated for the Massachusetts Institute of Technology using "normc1" uranium.

A new TRIGA Fuel Fabrication Facility was subsequently constructed at General Atomics, and in April 1975, transfer of usable equipment from the

" Hot Suite" to the new building began.

In May 1975, contaminated components were removed from the Hot Suite and disposed of as contaminated waste and facility decontamination efforts began.

The building was then decontaminated to very low levels; less than 500 counts per minute alpha fixed contamination (measurements were made on a grid with a portable alpha counter) and less than 20 dpm/100 cm2 removable contamination (Reference 8).

TARGET CRITERIA FOR UNRESTRICTED RELEASE The following approved target criteria have been taken from Reference 7.

Table 1 (Attachments 6A and 6B) is taken from USNRC's and State of California's (respectively) criteria for releasing facilities and equipment to unrestricted use.

It has been incorporated into our SNM-696 and State of California licenses.

The 10mits in this table were used for releasing concrete and other surfaces at the facility to unrestricted use.

RADIATION DETECTION EQUIPMENT The following radiation detection equipment was used for the various surveys.

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1.

Beta / gamma counters

a. Model TtM 28 and Model TBM 15 geiger counters manufactured by 1

Technical Associates were used to survey surfaces for beta / gamma l

contamination.

The instruments contain a pancake geiger mueller 2

(GM) detector which has a window thickness of less than 7 mg/cm,

l-The instrument has three ranges covering from 0-50,000 counts.per l

minute (cpm).

l 2.

Alpha counters

a. Model 12 rate meters with Model 43-44 air proportional alpha probes manufactured by Ludlum Measurements Inc. were used to survey equipment and surfaces for alpha contamination.

The instrument has four ranges covering from 0-500,000 counts per minute.

b. Model 12 rate meters with Model 43-1 scintillation alpha probes manuf actured by Ludium Measurements Inc. were used to survey equipment and surfaces for alpha contamination.

The instrument j

has four ranges covering from 0-500,000 counts per minute.

3.

Gamma Detectors

a. Model 19 microR meters (containing a NaI scintillation detector) manufactured Ludium Measurements Inc. were used to survey the fooms.

b. Gamma spectral analysis on selected samples of concrete and soil samples from the Stage 1 areas were done using a high purity germanium detector manufactured by Canberra Industries, Inc.

4.

Wipe Analysis Wipe samples collected throughout the Stage 2 rooms after clean up cperations were counted using a Model 2404 low-level alpha beta gamma counting system manufactured by Canberra Industries, Inc.

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All portable instruments are calibrated semiannually using a-nominal 30 curie Cs-137 source except the Ludium Model 19 which is i'

calibrated by the manufacturer.

The alpha / beta system has been calibrated for the various types of samples. This calibration is checked on a daily or weekly basis depending on usage.

p The final survey results have been converted from cpm (counts per minute) for a particular detector to dpm/100cm2 by correcting the counts per minute observed by appropriate detector. readings for background, detector efficiency and geometric factors associated with the instrumentation.

===1.

Background===

A " standard" natural background'was determined for each type of detector and subtracted from the survey readings.

2.

Efficiency Portable beta / gamma (GM) and alpha counters were calibrated to determine their efficiencies for uranium after analyses of samples of contaminated' concrete from the Stage 1 areas showed uranium contamination (the U-235 enrichment varied from 3-10%).

1 In order to simulate the conditions on'the concrete surfaces, concrete blocks having an area of approximately 25.cm x 25'em previously spiked with NBS traceable standard liquid solutions of depleted uranium and 93 percent enriched uranium to the average allowable release levels listed in Table 1.

The average allowable level for an area one meter by one meter or less is 5000 dpm/100 2 and the maximum allowable level is 15,000 dpm for an area less cm than 100 cm2 (Attachments 6A and 6B).

Surface measurements of the blocks were obtained with the instruments to determine the average allowable epm.

Since the blocks were for depleted uranium and 93%

enrichments, and the enrichment varied from 3-10%, the strictest limits of these two (the 93% enrichment standard) was used for determining the allowable limits.

Percent efficiencies 8

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were obtained to convert the readings in counts per minute (cpm)

L to disintegrations per minute (dpm).

3.

Geometry Correction The values listed in Table 1 (Attachments 6A and 6B) are in dpm/100 2

-cm, therefore, a correction factor was applied to the values to-correct for the smaller area of.the detector. The TBM-28 and TBM-15's have 5 cm diameter detectors which measures a 19.6 cm2 j

i area. The reading is' corrected by multiplying by 5.1.

The alpha detectors used for the surveys "see", at any given time, an area of 2

78.7 cm, which then' requires a correction factor of 1.27.

i about INITIAL SURVEY AND DECONTAMINATION EFFORTS All the equipment (primarily telecommunications equipment) from the Stage 2 area was transferred to a temporary location.

The carpet installed over the original concrete floor was removed.

l-An initial survey (Attachment 7) was conducted in the area to i

determine if there was any detectable contamination. Radiation 1

measurements.using a geiger counter showed contamination primarily along the cracks on the concrete and along the northwest side of the floor of room 40.

A beta / gamma contamination survey on the surface of j

the concrete floor was conducted (measurements were made with Model j

TBM-28 and Model TBM-15 geiger counters). Low beta / gamma levels were j

detected 1.e. up to 1200 counts per minute (epm) on several small floor j

areas in.the Stege'2 rooms.

The walls (north, south and west) were surveyed up to two (2) meters abeve tne floor (the east wall is a new wall and was not part of the " Hot Suite" area). A small localized area along the west wall of room 40 (adjacent to the floor) was contaminated (~1000 cpm beta / gamma). No other contamination was detected on the walls.

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E The Stage 2 " Hot Suite" area has been conservatively estimated to be about 587 ft2

~About nine (9) ft2 of the 587 ft2 required decontamination;'which represents ( 2 % of the Stage 2 area. The_ floor.

l area decontaminated in each' room is provided in the table below:

i Approximate Approximate Total-Area 2

Room Area (ft2)

(ft 1 Decontaminated-Stage 2 Room 40 106.

~2.0 Room 41 81

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Room 42 94 0

. Room'43 94

~0.1 Room M 212

~1.3 Total Stage 2 587

~8.7 FINAL RADIATION SURVEYS Table 1 (Attachments 6A and 6B) provides acceptable (approved) limits for fixed contamination levels. Final radiation surveys of the Stage I rooms which were cleaned and/or scabbled were conducted. The measurements 2

2 of average contamination (in dpm/100 cm ) were averaged over 1 M area or 2

less. ~The maximum contamination level (also in dpm/100 cm ) applies to an-2 area of not more than 100 cm. The final floor survey is provided in.

The final wall surveys are provided in Attachment 9.

A microR meter was also used to survey the rooms and to measure l

radiation levels.

The final surveys show the measurements obtained on the surface at several locations.

These levels were all within normal background levels. The results of this survey are provided in

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Alpha counters were also used to survey the rooms. Very low j

1.e. ( 60 cpm (if any) levels of alpha contamination were detected.

The beta / gamma levels were used to determine allowable release levels for the 1

1 uranium contaminated areas.

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FINAL CONTAMINATION SURVEYS Table 1 (Attachments 6A and 6B) provides limits for acceptable removable surface contamination levels. Wipes were collected en the floors of the rooms. The wipe sample locations are shown in Attachments 9 and 10 (floor and wall, respectively). The results are provided in 1.

The contamination levels in every location were ( 20 dpm/100 cm2 and well below the Table 1 limits (Attachment 6A and

area, 6B) for removable contamination.

COMPLIANCE WITH THE TARGET CRITERIA Facilities and Equipment Concrete and other surfaces of the Stage 2 rooms were cleaned to levels below the limits in Table 1.

The final surveys provided in this report demonstrate compliance.

Direct Radiation The direct radiation levels in all areas of the Stage 2 areas are l

at or below normal background levels.

CONCLUSION Stage 2 rooms of the former TRIGA Fuel Fabrication " Hot Suite" area formerly located in the northwest corner of the Experimental Building (Building 9) have been decontaminated to levels below the specified limits and therefore meet the criteria for release to unrestricted use.

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REFERENCES 1.

Asmussen, Keith E., letter # CAL-1095 to Mr. Ben Kapel, " Final Survey Report on the Decontamination of GA Technologies' Experimental Building", dated July 28, 1987.

2.

Kapel, Ben R.,

letter to Keith E. Asmussen dated May 14, 1987.

Docket #033087-0145, containing amendment #86 to GA's radioactive material license number 0145-80.

3.

Montgomery, James L.,

letter dated October 1, 1987 to R. N.

Rademacher, " Inspection at GA Technologies, Inc. (Confirmatory Survey), with Report No. 70-734/87-11.

4.

Asmussen, Keith E.,

letter #696-1337 to Mr. Robert D. Thomas,

" Request for ' Confirmatory Survey (Experimental Building -

Stage I",

dated January 30, 1989.

5.

Asmussen, Keith E., letter # CAL-1340 to Mr. Gerard Wong,

" Request for Release of Certain Portion of GA's Experimental Building (Stage I)", dated January 30, 1989.

6.

Yuhas, Gregory P., letter dated August 18, 1989 to R.

N.

Rademacher, "NRC Inspection" with ORAU final report 89/F-98 dated July 1989.

7.

Asmussen, Keith E.,

letter # CAL-1049 to Mr. Ben Kapel,

" Decontamination of GA Technologies' Experimental Building,"

dated March 27, 1987.

8.

Letter dated 8/5/75, J. M. Keith to F. O. Bold.

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d ATTACHMENT'5:

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ATTACHMENT 6B j

-.1 TABE I l

. o--

ACEPTABLE SURFACE CCKfAMINATION EVELSVF j

a c.

IUCLIE" AVtRAGE' fiAXItUf d RRO/ABE'

2 (dpm/100 cm )

(dpm/100 cm )

(dpm/100 e=2) s) U-nat,. U-235,- U-238, and

.5,000 15,000 1,000 accociated decay products

))TTransuranics, Ra-226,. Ra-228, 100 300 20 l

~ Th-2 30, Th-228, Pa-231'

'Ac-227, f-12t, I-120

) Th-n a t, Th-232, Sr-90 1,000 3,000 200 Ra-223, Ra-224, U-232, I-126, I-131, I-133 n ta-gamma emitters (nuclides 5,000 15,000 1,000 1) e with decay modes other than I

alpha emission or spontaneous

' fission) except Sr-90 and others noted above.

)

))

H-3, C-14 except as DNA 20,000 60,000 4,000 pracursors f,/

hora surface contamination by both alpha-and bets-gamma-emitting nuclides exists, the limits stablished for alpha-and beta-ganna-emitting nuclides should apply independently.

2 usxd in this table, dpm (disintegrations per minute) means the rate of emission by radioactive 29terial as determined by correcting the counts per minute observed by an appropriate detector-

'cr background, efficiency, and geometric factors associated with the instrumentation.

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

For 9bjscts of less surface area, the average should be derived for each such object.

The maximum contaminscion level applies to an area of not more than 100 cm.

"he amount of removable radioactive material per 100 cm of surface area should be determined 1; wiping that area with dry filter or soft absorbent paper, applying moderate ' pressure, and 1sssssing the amount of radioactive material on the wipe with an appropriate instrument of known

?!!i cicncy.

When removable contandnation on objects of less surface area is determined, the hartinent levels should be reduced proportionally and the entire surface should be wiped.

DNA precursors mean molecules. or compounds that are directly incorporated into the DNA molecule furing DNA biosynthesis, e.g. purine and pyrimidine bases and their analogs, nucleotides and Buclcosides.

The acceptable surface contandnation levels for H-3 and C-14 in DNA precursors Jro as tabula ted in paragraph (d) for beta-gamma-emitters.

' USHRC Regulatory Guide 1.86 Termination of Operating Licenses for Nuclear Reactors _, Waahington,

D.C.

(June 1974)

? ANSI, Control of Radioactive Surface Contandnation on Materials, Equipment and Facilities i To Be Released for Uncontrolled Use, final draf t, oroposed American National Standard N-328, Atomic industrial Forum, Inc., N.Y.

(June 1974)

_,..',c 1

4 7

INITIAL SURVET T 'DE "IOT SUI'IE" STME 2 FIIXR AREAS H

20'7"-

=!

h\\

e a amma ea ngs 450 '

Room 40 in-un s Per Muute j

750 cpm cpm g

800 cpm N

1200 c p m_

1000 cpm #% / / / // '

500 cpm

\\

' Floor and Wall

- 350 cpm

+

350 comb Room 42 29' 8" 25' 6" Rm U A

3 1000 cpm Ctn U

f

?-

H 12' 9" Notes:

l

[

1.

Initial survey cmpleted on the concrete floor after removal of the carpet. Survey ccupleted on May 23, 1989 using a Model TBM-28 geiger counter (#92238) calibrated February 9, 1989, and on August 22-23 using Model TBM-28 geiger counter (#2759) calibrated 8/14/89.

l 2.

MicroR meter measurements using a Model Ludlum 19 survey meter (#34915) calibrated February 8, 1989 were all 10 microR/hout except for a small spot in rocan 41 which measured ~ 15 microR/ hour.

3.

Alpha surface measurements using a Ludlum 12 ratemeter (#46452) with an alpha probe (model #43-1) calibrated January 20, 1989.

4.

Contamination was detected primarily along the cracks in rocxus 40 and 41.

Contamination was also detected along the west floor area of roam 40 (**1000 cpn). Small " spots" rpMing ~350-1000 cpn (beta /ganna) were found in the roces.

5.

The concrete was scabbled along the cracks and " spots" until levels were below allowable release levels.

1.

.f H.

.,u...,

ATTACHMENT 8 FINAL SURVEY OE' 'lHE.

"H01' SUTIE" STAGE 2 FilXR AREAS s=

20' 7" h

Room 40 Room 41

~[

N 0

0 0

0

'0 0

0 0

6660 0 0

0 o

O' O

O O

O O'

O O

O 5994 0 0

0 0

Room 42 0

0 0-0 0

0 0

0 29' 8" 25' 6" 0

0 0

3330 0 0

0 0

Room 43 0

0 0

0 p

Room 47

/

0 0

u O

O O

12' 9" %y

=

Notes:

1.

Ievels were measured on concrete floor after cleaning or scabbling.

2. - Final survey cartpleted August 22-23, 1989 using TBM-28 geiger counter (# 2759) calibrated August 14, 1989, and on August 24, 1989 using Model TBM-15 (#108113) mlihrated May 2,1989) 3.

Fach'.init represents a three foot by three foot area or less.

2 4.

Top value is the average beta /gs:rna contamination in DPM/100 cm in a three foot by three foot area or less.

5.

Bottcan value is the mav4mnm beta /garana contamination in DPM for an area less than 100 cm#.

______ _ D

( ;' J. :.. '. ?

4

.y.

9

...:~...

MTRQRENT 9 SURVEYS T THE "fDT SOTIE" STRGE 2 ROCM MRILS INITIAL JDO FINAL SURVEY T M MRIE MRIL

=

20' 7"

-H I

0' O

-0 0

0 0

G 0

0 0

h h

2 meters 0

0 0

u Oz O

O O

O INITIAL AND F_INE SORVEY T 'DE SO[TIH MRLL

!=

12' 9" O

ce temime ue s- - v A

0 0

Locations'(See 2 meters 17 18 Attachmeet 11 for 0

0 0

Re s'si t s )

p 0

0 0

INITIAL SORVEY T E 1EST MRIL (cm pleted 8/23/89 using TBM-2759)

=

29 ' 8 "--

r:

0 0

0 0'

2 meters 0

0 0

920 0

0 p

FDEL SORVEY T TfE DEST MRIL 29' 8"

=-

0 0

0 h

h 2 meters 0-0 0

0 0

0 i

y -

0 0

Notes:

I-1,. Levels were measured on concrete floor after cleaning or F'ahh14ng.

2.

[Inital survey of the west wall shows levels in counts per minute (background subtracted)]. Final surveys empleted August 22-23, 1989 using TBM-28 geiger counter (# 2759) calibrated August 14, 1989, and on l'

August 24, 1989 using Model TBM-15 (#108113) t'alibrated May 2, 1989) 3.

Each unit reprecents a three foot by three foot area or less 4.

Top value is the average beta /ganma contamination in DPM/100 cm in a three foot by three foot area or less. (Final surveys) l-5.

Bottom value is pe wrr4mm beta /ganma contamination in DPM for an area less than 100 cm. (Final surveys)

[

~,p

.a.

ea

..4 MTRCIMNr 10 ONDMINK

' SORVET. IDCATIWS AND MICRO R/HR RADIM. s IEVELS m STAGE 2 FICOR ARENi 20' 7"-

>-1 M

Room 40 Room 41 B

@ @T

/ a e

g g

29' 8" 25' 6" Room 42 10 Room 43 y

V to to f

y Room 47 l

l 1Q' 9" &

Notes:

1.

Circled numbers are wipe locations.

2.

Numbers in squares are microR/ hour surface radiation levels.

1..

V l

L

' ATTACHMENT 11 CONTAMINATION SURVEY RESULTS L

" XUO 2 41989 GROSS ALPHA / BET A COUNTIt4G RESULTS FOR WIPE SAMPLES ALPHA BETA COUNT SAMPLE ID LENGTH DPM/100 SQ.CM.

% ERROR DPM/100 S0.CM.

% ERROR MIN 95% CL 95% CL 09W-1 Room 47 1.

6.322E-01 149.83

<9.111C-01 95 00 2

40-47 Room 47 1.

<1.089E-02 95.00 (3.248E-02 95.00 3 8/23/89 Room 47 1.

<1.089E-02 95.00

<3.693E-01 95.00

)

Room 40 1.

2.905E-01 230.60

<1.402E 00 95.00 4

5 Room 40 1,

2,905E-01 230.60

<9.111E-01 95.00 6

Room 40 1.

<1.089E-02 95.00

<3.693C-01 95.00 7

Room 40 1,

2.905E-01 230.60 (3.693E-01 95.00 8

Room 41 1.

2.905E-01 230.60 (3.248C-02 95.00 9

Room 41 1,

2,905E-01 230.60

<3.693E-01 95.00 10 Room 42 1.

6.322E-01 149.83 (1.402C 00 95.00 11 Room 42 1,

ei,og9E-02 95.00

<3.248E-02 95.00 12 Room 42 1.

2.905E-01 230.60 (3.693E-01 95.00 13 North Wall 1.

2.905E-01 230.60 (9.111E-01 95.00 14 North Wall 1.

<1.089E-02 95.00

<3.693E-01 95.00 l5 West Wall 1.

<1.089E-02 95.00

<3.693C-01 95.00 16 West Wall 1.

<1.089E-02 95.00

<9.111E-01 95.00 17 South Wall 1.

<1.089E-02 95.00

<1.402E 00 95.00 10 South Wall 1,

(1,og9E-02 95.00 (9.111E-01 95.00 AVERAGE 1.886E-01 6.358E-01 HIGH 6.322E-01 1.402E 00 LOW 1.089E-02 3.248E-02 STAGE 2 AREAS NOTE: THE ERRORS DO t40T INCLUDE INHERENT EFFICIENCY CALIBRATION UNCERTAINTIES.

NOTE:

SEE ATTACHMENTS 9 and 10 FOR LOCATIONS

ML20248C442

Text

= = = = =

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