ML20065N076

Confirmatory Radiological Survey of Berkeley Research Reactor Facility Univ of CA at Berkeley,Berkeley,Ca

ML20065N076
Person / Time
Site:	Berkeley Research Reactor
Issue date:	11/30/1990
From:	Vitkus T OAK RIDGE ASSOCIATED UNIVERSITIES
To:	NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20065N073	List: ML20065N070 ML20065N076
References
ORAU-90-K-53, NUDOCS 9012110314
Download: ML20065N076 (62)

Text

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l OR AU 90%53 I

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Pr by CONFIRMATORY RADIOLOGICAL SURVEY

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un,wers*.

OF THE P

ar the BERKELEY RESEARCH REACTOR FACILITY I

Reg a o u

r UNIVERSITY OF CALIFORNIA s n's g

Region V Office AT BERKELEY Spi,Tn'd by BERKELEY, CALIFORNIA r

I Industrialand Medical Nuclear Safety T. J. VITKUS I

and Division of Radiation Safety and Safeguards.

I Emergency Preparedness and Radiological Protection Branch I

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I Environmental Survey and Site Assessment Program Energy / Environment Systems Division FINAL REPORT NOVEMBER 1990

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I' il ll NOTICES The opinions expressed herein do not necessarily reflect the opinions of the sponsoring institutions of Oak Ridge Associated um 1

Univorattles.

This report was prepared as an scoount of work sponsored by the United States Government. Neither the United States Government nor the U.S. Department of EnerDY. nor any of their employees, makes any warranty, express or impiled, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, mark manuf acturer.or otherwise. does not necessarily constitute or imply 3

its endorsement or recommendelsn,or favoring by the U.S. Government or any agency thereof.The views and opinions of authors i

Orpressed herein do not necessarily state or reflect the,se of the U.S. Government or any spency thereof.

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I OR AU 90%53 l

CONFIRMATORY RADIOLOGICAL SURVD' I

OF TIIE BERKELEY RESEARCII REACTOR FACILITY I

UNIVERSITY OF CALIFORNIA AT BERKELD' 1

BERKELEY, CALIFORNIA l

Prepared by Timothy J. Vitkus Environmental Survey and Site Asser.sment Program Energy / Environmental Systems Division I

Oak Ridge Associated Universities Oak Ridge, Tennessee 37831-0117 Project Staff J. D. Berger M. A.

Laudeman J. P. Evans

• E. A.

Powell E

L F. Friedman R. B.

Slaten W

R. C. Gosslee C. F. Weaver l

Prepared for Division of Industrial and Medical Nuclear Safety l

and Division of Radiation Safety and Safeguards Emergency Preparedness and Radiological Protection Branch I

U.S. Nuclear Regulatory Commission Region V Office FINAL REPORT NOVEMBER 1990 I

This report is based on work performed under an Interagency Agreement (NRC Fin.

No. A 9076) between the U. S. Nuclear Regulatory Commission and the U. S. Department g

of Energy.

Oak Ridge Associated Universities performs complimentary work under contract number DE AC05-760R00033 with the U. S. Department of Energy.

l

• DOE Summer Intern currently attending the University of North Carolina.

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I CONFIRhiATORY RADIOLOGICAL SURVEY I-OF TIIE BERKELEY RESEARCII REACTOR FACILITY UNIVERSITY OF CALIFORNIA AT BERKELEY I

BERKELEY, CALIFORNIA I

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Prepared by:

Date:

T. J.Nitkus, Project Leader

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Emironmental Survey and Site Assessment Program I-Reviewed by: _

4:rh Date: 8/fM/)

D. Be'rger, % gram Director

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Environmental Survey and Site Assessment Program I

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Reviewed by:

C E, LA) 3LaAA Date: "l9 90 C. F. Weaver, Laboratory Manager Emironmental Survey and Site Assessment Program I

/((7 8 Approved byfh Aru

1. D Date:

R. Cloutier, Assistant Chairman Energy / Environment Systems Division I

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I TABLE OF CONTENTS g

PAGE LIST O F FIG URES...........................................

ii LIST O F TAB LES............................................ iv l

INTRO D U CTION.............................................

1 FACILITY D ESCRIPTIO N......................................

2 P R OCE D URES..............................................

2 FINDINGS & RESULTS........................................

5 COMPARISON OF RSSUL.TS WITH GUIDELINES....................

7 S U MMAR Y.................................................

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R EFEREN CES..............................................

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APPENDICES Appendix A: Major Sampling and Analytical Equipment I

Appendix B: Measurement and Analytical Procedures I

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I LIST OF FIGURES g

PAGE FIGURE 1:

City of Berkeley, CA Showing Campus Area............... 10 I

FIGURE 2:

Plot Plan Showing Campus Area and Etcheverry Hall......... 11 l

FIGURE 3:

UC Berkeley Etcheverry Hall.......................... 12 FIGURE 4:

Vertical Section Berkeley Research Reactor................ 13 I

FIGURE 5:

Section Through Etcheverry Hall....................... 14 l

FIGURE 6:

UC Berkeley Etcheverry Hall Ground Floor Nucleonic Lab and Enviro ns.................................. 15 FIGURE 7:

Section Through Etcheverry Hall Showing Background Exposure Rate Measurement Locations.......... 16 FIGURE 8:

UC Berkeley Etcheverry Hall Showing Exposure Rate Measurement Locations.............................. 17 FIGURE 9:

Room 1140, Emergency Egress, and Room 1110B Direct Measurement Locations and Ground Floor Exposure Rate l

Measurement Locations.............................. 18 FIGURE 10: Elevation North Wall, Room 1140...................... 19 FIGURE 11: Elevation South Wall, Room 1140...................... 20 l

FIGURE 12: Elevation East Wall, Room 1140....................... 21 FIGURE 13: Elevation West Wall, Room 1140....................... 22 FIGURE 14: North Wall, Reactor Monolith Eterior................... 23 FIGURE 15: South Wall, Reactor Monolith Exterior................... 24 g

FIGURE 16: Operator's Platform Walking Surface.................,.. 25 FIGURE 17: Monolith Mezzanine................................ 26 ii I

I LIST OF FIGURES (Continued)

I PAGE g

FIGURE 18: Reactor Monolith Walking Surface...................... 27 FIGURE 19: Reactor Monolith Exposure Room and Pool Floor........... 28 I

FIGURE 20: Reactor Monolith Interior North Wall.................... 29 l

FIGURE 21: Reactor Monolith Interior South Wall...................

30 FIGURE 22: Reactor Monolith Interior-East Wall..................... 31 FIGURE 23: Reactor Monolith Interior West Wall.................... 32 FIGURE 24: Reactor Monolith Exposure Room Ceiling................. 33 FIGURE 25: BRR Exposure Room Door........................... 34 g

FIGURE 26: BRR Thermal Column Door.......................... 35 I

FIGURE 27: Vertical Column Plug............................... 36 l

FIGURE 28: Developed View of Storage Well Room 1140............... 37 FIGURE 29: Reactor Operator's Office............................. 38 I

FIGURE 30: Decontamination Facility Floor and Walls................. 39 h.

FIGURE 31: UC Berkeley Etcheverry Hall Showing Soil Sampling Locations.. 40

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,gW LIST OF TABLES PAGE i

TABLE 1:

Exposure Rate Measurements......................... 41 I

TABLE 2:

Summary of Surface Acthity.........................

42

, l TABLE 3:

Radionuclide Concentrations in Soil....................

44 TABLE 4:

Radionuclide Concentrations in Concrete.................. 45

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I CONFIRMATORY RADIOLOGICAL SURVEY OF THE I

BERKELEY RESEARCII REACTOR FACILITY UNIVERSITY OF CALIFORNIA AT BERKELEY BERKELEY, CALIFORNIA I

INTRODUCTION I

The University of California at Berkeley (UCB) operated a 1 MW TRIGA Mark III Reactor from August 1966 through December 1987, with a total power output during this period of 292.5 mwd. The Berkeley Research Reactor (BRR) was located in Etcheverry i

g Hall on the UCB campus in Berkeley, California (Figures 1 3). The unit was a General Atomics heterogenous pool type reactor (Figure 4) and provided a source of ionizing l

radiation and neutrons for research projects as well as a training mechanism for students in reactor operation principles.

Operation was in accordance with AEC/NRC l

License No. R 101 (Docket No. 50 224).

Reactor operation activities resulted in the activation of core components, surfaces of the exposure room, ends of beam ports closest to the reactor, and concrete around beam ports and thermal columns. Other reported localized contamination, within the reactor bay, was the result of past experimental work with tritium and natural uranium. These experiments were conducted under a California Radioactive Materials License.

I After shutdown of the reactor in 1987, the fuel was removed and shipped off site during June and July of 1989. This was followed by the issuance of the NRC order, on September 12,1989, authorizing reactor dismantlement. The reactor was decommissioned by removing the water from the tank followed by dismantlement and disposal of activated reactor components and support equipment, and scarification of activated concrete within g

- the reactor tank.

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I Once decommissioning was completed, a survey of the reactor environs, conducted by the licensee's agent, demonstrated that the residual radiation levels satisfy the established I

NRC guidelines. The Region V Office of the NRC requested that the Environmental Survey and Site Assessment Program of Oak Ridge Associated Universities (ORAU) conduct a survey of the facility to confirm those findings.

I FACILITY DESCRIPTION I

Etcheverry Hall is a six story brick structure comprised of classrooms, laboratories, g

and offices with the reactor facility located on the basement level (Figure 5). The reactor facility is constructed with concrete floors, block and reinforced concrete walls and ceilings.

l The following areas were included as part of the ORAU survey: the high bay reactor 2

room (Room 1140) measuring approximately 924 m, an emergency egress measuring

,l 2

2 2

30 m, the reactor operators office (15 m ), the personnel decontamination facility (22 m ),

an airlock, a rabbit fume hood terminus located in Room 1110B, and adjacent corridors (Figure 6). Room 1140 is divided, by means of temporary confinement barriers, into a DECON area and an adjacent State of California Radioactive Materials licensed area which was not included in this survey. Additional coverage of the California Radioactive Materials License 1333 62 includes sealed neutron sources contained in a storage well in Room 1140 and Room 1110B exclusive of the previously described hood.

PROCEDURES I

Objective I

On July 16 - 18, 1990 ORAU conducted a confirmatory survey of the Berkeley g

Research Reactor (BRR) facility. The purpose of the survey was to verify the adequacy I

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I and accuracy of the licensee's final survey and to confirm the radiological condition of the facility relative to decommissioning guidelines.

Document Review I

ORAU reviewed the licensees's final survey report supporting the decommissioning of the reactor.

I Survey Procedures I

1.

The reference grid established by the licensee was utilized by ORAU during the l

course of the survey. The grid consisted of 1 m x 1 m blocks in areas designated as high contamination potential areas. These areas included the reactor itself and l

immediate area, operators office, emergency egress, and personnel decontamination room. The remainder of the facility was divided into 3 m x 3 m blocks.

2.

Gamma radiation scans to identify locations of residual activity were performed on lower walls and floors of Room 1140, the reactor operators office, personnel decontamination room, airlock, basement corridors, the hood in Room 1110B, the roof, storm and sanitary sewers, and immediate exterior grounds of Etcheverry Hall.

Scans were performed using Nal(TI) gamma scintillation detectors coupled to I

countrate meters with audible indicators.

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3.

Large area and/or 100 cm hand held gas proportional detectors were used to scan floors, lower walls, and equipment for alpha plus beta activity. Accessible ceilings, pipes, ducts and other overhead structures were scanned with thin window GM g

detectors. All detectors were coupled to countrate meters / scalers with audible indicators.

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Gamma radiation exposure rate measurements were obtained at one meter above surfaces at various locations in and around Etcheverry Hall (Figures 7,8, and 9).

Background measurements were obtained at locations within Etcheverry Hall that have similar construction but no history of radiological usage.

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5.

Measurements to determine surface activity levels were performed on randomly selected grid blocks located on the floors, lower walls, and hoods (Figures 9 - 30).

Measurements were performed at the center and four points equidistant from the center and grid block corners. Gas proportional detectors for identifying alpha plus l

beta activity were utilized for these measurements. Single point measurements were performed on upper walls and accessible ceilings within Room 1140, the reactor l

operators office, and the airlock floors and walls using gas proportional and or GM detectors (Figures 9 - 30) All detectors were coupled to countrate meters / scalers.

l During the course of the survey, the radiological condition of the facility was determined to be such that extensive upper wall and ceiling measurements were not required. Additionally, established release criteria as well as site radiological history did not necessitate discrimination of alpha and beta activity levels in the absence of elevated measurements.

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Smear samples, for determining removable activity levels, were collected from the l

location within each surveyed grid block with the highest total direct measurement, from each single point measurement location, drains, sewers, and hoods.

7.

Soil samples were collected from areas with elevated gamma radiation levels.

8.

Concrete samples were collected from within the reactor r onolith.

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I FINDINGS AND RESULTS Surface Scans I

Surface scans for alpha plus beta activity did not identify any areas of elevated contact radiation levels. Gammt scans inside Etcheverry Hallidentified one location with elevated activity. This area was associated with a laboratory bench, situated along the north wall g

of Room 1140. Further investigation revealed an encapsulated check source which was removed and returned to appropriate UCB personnel; gamma radiation returned to l

background levels following source removal. Gamma scans of the exterior of Etcheverry Hall identified two areas of elevatt. activity located in the west alley adjacent to the l

building (Figure 31).

Exposure Rate Measurements Exposure rate measurements and locations are given in Table 1.

Background

measurements were 7 gR/h to 9 pR/h at one meter above surfaces. Final exposure rate meesurements for the reactor facility and immediate environs ranged from 8 pR/h to 10 pR/h.

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. Surface Activity Levels The results of total and removable surface activity measurements are summarized in Table 2.

Most of the measurements were below the lower limits of detection for the g

procedure.

The highest grid block average for total alpha plus beta activity was 2

2 440 dpm/100 cm. Removable activity measured in grid blocks was <8 dpm/100 cm for l

alpha and <18 dpm/100 cm for beta. Total activity levels for single point measurements 2

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2 were <250 to 1700 dpm/100 cm for alpha plus beta and <840 dpm/100 cm for beta-2 2

gamma. Removable activity levels were <8 dpm/100 cm for alpha and <18 dpm/100 cm 2

2 for beta. Removable tritium activity levels were <22 dpm/100 cm to 43 dpm/100 cm,

Radionuclide Concentrations in Concrete I

Concentration levels of anticipated activation and fission products are presented in Table 4. All radionuclides were below the minimal detectable activity for the analysis, with the exception of Co-60 which had a concentration range of 0.4 e 0.4 pCi/g to 2.3 1.6 pCi/g.

l No guideline levels for Co 60 in building materials have been established for this site. The exposure pathway for Co-60 is direct gamma radiation. Although there is l

evidence of low levels of this activation product in the concrete, exposure rates in the facility are well below 5 pR/h above background, and therefore the measured l

concentrations of Co-60 are considered such that the basic release criteria is satisfied.

Elevated Area Synopsis The elevated contact gamma radiation levels detected were located in the west alley adjacent to Etcheverry Hall (Figure 31). The alley is a public access area and is I

outside the NRC license jurisdiction. The anomalies identified were the result of a surface layer of a light brown material with a consistency of fine sand that appeared to have been placed over the indigenous soils.

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I Gamma exposure rate measurements were performed and surface samples collected from three (3) locations. Exposure rates ranged from 10 pR/h to 13 pR/h at one meter above the surface. UCB personnel excavated the material and the area was resurveyed by collecting confirmatory soil samples and performing a gamma exposure rate measurement from the area exhibiting the highest contact gamma activity.

I Concentrations of radionuclides in samples collected from the alley are summarized in Tabie 3. Concentrations of radionuclides in the post remediation sample are as follows:

U 235, 0.5 0.2 pCi/g; U 238, 4.4 2 1.3 pCi/g; Total U,17 pCi/g; Th 232,1.2 l

0.4 pCi/g; Ra-226, 3.8 0.4 pCi/g.

l The radionuclides present and their respective concentrations, indicate that the material contains natural unprocessed uranium including daughter products. The NRC l

license for the Reactor Facility did not include the possession and use of unprocessed uranium. Based on this information and the location of the material in a public area, the material is likely a com.mercial product such as blasting grit and is not associated with NRC licensed activities.

The final maximum gamma exposure rate measurement for the remediated areas I

was 9 gR/h which is within the 7 to 9 4R/h site. background levels.

COMPARISON OF RESULTS WITII GUIDELINES

- The NRC guidelines for surface activity, established for release of the Berkeley Research Reactor to unrestricted use, are based on the following:

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U nat, U 235, U 238 and associated decay products 2

2 15,000 dpm/100 cm (maximum in a 100 cm area)

I 5,000 dpm/100 cm (averaged over 1 m#)

2 2

1,000 dpm/100 cm, removable Residual Beta-Gamma Emitters 2

2 15,000 dpm/100 cm (maximum in a 100 cm area) g 5,000 dpm/100 cm (averaged over 1 m )

2 2

2 1,000 dpm/100 cm, removable I

All measurements conducted during this survey were well within these guideline levels.

The guideline for gamma exposure rate is 5 pR/h above background at 1 m from surfaces. The maximum level measured in the facility was 9 gR/h; the maximum level outside the facility was 10 gR/h. These levels are less than 5 gR/h above the area background level of 7 to 9 gR/h which meets the established guideline.

SUMMARY

On July 16 - 18, 1990 Oak Ridge Associated Universities performed a confirmatory radiological survey of the Berkeley Research Reactor located in Etcheverry Hall on the g

University of California, Berkeley Campus, in Berkeley, California. The survey included surface alpha plus beta, beta gamma, and gamma scans, direct and removable activity level I

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I measurements, and soil and concrete sampling. The findings support the close out survey performed by the licensee, and confirm that the radiological conditions of the BRR facility I

satisfy the NRC guidelines for release to unrestricted use.

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23

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5 I

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LOCATIONS A SINGLE P0lNT h--sm= W

=

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23 I

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I FIGURE 15: South Wall Reactor, Monolith Exterior 24

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~

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2 I

I MEASUREMENT LOCATIONS

{ GRID BLOCK A SINGLE POINT w -= $

-=

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g I

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/

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28 I

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FIGURE 20: Reactor Monolith Interior-North Wall I

I 29

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l

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32

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LOCATIONS

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36

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FIGURE 29: Reactor Operator's Office I

38 l

l

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2FL 2FM 2FN 2FO 2FP2F02FR 2FS 2FT 2FU 2FV 2FW 2FX 2FY 2FZ2GA2GB 2GC 2GD 2GE 1

%)

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LOCATIONS

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I FIGURE 30: Decontamination Facility Floor and Walls 39

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FIGURE 31: UC Berkeley-Etcheverry Hall Showing Soil Sampling Locations g

g 40

1I TABLE 1 l

EXPOSURE RATE MEASUREMENTS BERKELEY RESEARCII REACTOR FACILITY UNIVERSITY OF CALIFORNIA AT BERKELEY l

BERKELEY, CALIFORNIA Exposure Rate (uR/h)

Location at 1 m Above Surface I

l Background Measurements Exterior' North Etcheverrey Hall 8

l Exterior' East Etcheverrey Hall 9

Exterior' South Etcheverrey Hall 7

Exterior' West Alley Etcheverrey Hall 8

Interiod Third Floor Lobby 8

Interior

• Fifth Floor / Center of East Corridor 8

6 Interior -

Fifth Floor / South End of East Corridor 9

I Interior

• Sixth Floor / Center of East Corridor 8

6 Interior Sixth Floor / South End East Corridor 9

Reactor Facility & Elevated Location Measurements Exterior' West Alley Etcheverrey Hall 12 Exterior' West Alley Etcheverrey Hall 10 I

Exterior ^d West Alley Etcheverrey Hall

-9 Interior Reactor Monolith 10 Interiof Reactor Bay (Room 1140) 9 l

Interior Reactor Operators Office 9

Interiof Airlock 9

Interiof Personnel Deconiamination Room 8

" Refer to Figure 8.

• Refer to Figure 7.

' Refer to Figure 9.

dMeasurement taken following remediation.

1 g

41 1

M M

M M

~M M

W M

M M

M M

M M

M M

TADLE 2

SUMMARY

OF SURFACE ACITVTIY BERKELEY RESEARCH REACTOR FACILFIY UNIVERSITY OF CALIFORNIA AT BERKELEY BERKEI.FY, CALIFORNIA Hiohest Gdd Block Avo.

Total Activity Removable Actmtv Tritium 2

1. Measured (dpm/100 cm')

(dpm/100 cm')

(dpm/100 cm )

(RemovatWe)2 Room Location Locations Alpha plus Beta Alpha plus Beta Range Alpha Range Beta Range (dpm/100 cm )

1140 Lower Walls and Floor 14

<240

<240 - 280

<8

<18

<22 Upper Wa!!s a Ceiling 45 N/A

< 840

<8

<18 EquipmeM &

Drains 5

N/A

< 840

<8

<18

<22 - 43 Reacter Wans and w

Pool &

Floor 27 440

<240 - 660

<8

<18

<22 Exposure Room Ceiling 1

<250

<250

<8

<18

<22 i

Exposure Door 4

<250

<250 A10

<8

<18

<22 Room Door Single Point 1

N/A 1700 Personnel Walls and Decon Floor 1

<240

<240

<8

<18

<22 i

i Reactor Lower Walls Operators and Floors 1

<250

<250

<8

<18

<22 Office Upper Walls and Ceirings 1

<270

<8

<18

M M

M M

M M

M M

M M

M M

M M

M TABLE 2 (Continued)

SUMMARY

OF SURFACE ACTIVTIY BERKELEY RESEARCH REACIUR FACILITY UNIVERSITY OF CALIFORNIA AT BERKELEY BERKELEY, CALIFORNIA -

i Hichest Grid Bloc.c Ava.

Total Actmtv Removable Activity Trith

1. Measured (dpm/100 cm3 (dpm/100 cmi (dpm/100 crrd (Remwable)2 Room Locahon Lix.danw A'pha plus Beta Alpha plus Beta Rcnge Alpaa Range Beta Range (dpm/100 cm )

i Airlock Wa!!s and

& Hall Floor 4

<250

<8

<18 i

To ReJor Room Vertical Wa!!s Thermal 1

<250

<250

<8

<18

<22 Column l

C Horizontal Thermal Door 2

<250

<250 - 420

<8

<18

<22 Column Door i

Emergency Wa$b and 1

<240

<240

<8

<18

<22 Egress Floor 11108 Hood 1

<250

< 250

<8

<18

<22 Sto:m &

Sanitary 4

Sewers 2

<8

<18

<22

[

t

TAliLE 3 I

RADIONUCLIDE CONCENTRATIONS IN SOIL BERKELEY RESEARCII RIMCTOR FACILITY UNIVERS!1Y OF CALIFORNIA AT BERKELEY

l BERKELEY. CALIFORNIA l

Sample Radionuclide Concentration (oCUc)

Location

• U 235 U 238 Total U' Th 232 Ra 226

'l m-,

d 1

2.9 0.4 77 12 138 12 2 0.3 73 1

'I 2

1.3 0.3 36 10 63 4.9 0.2 30 0.3 3

0.1 2 0.1 7.7 1.7 5.3 1.0 0.5 0.9 u: 0.2 46 Post 0.5 e 0.2 4A L3 17 1.2 e 0.4 3.8 0.4 l

Remediation

.. _,u, I

' Refer to Figure 31 for sample points, g

• Sample collected from area with highest contact gamma radiation level following 3

excavation, i

' Calculated, utilizing U 234lU 235 activity ratio of 21.

d g

Uncerta!ntier represent the 95% confidence level, based only on counting statistics; M

additionallaborattry uncerta!n'iea of 16 to 10% have not been propngated into these data.

I I

LI I

I I

44

I TABLE 4 I

RADIONUCLIDE CONCENTRATIONS IN CONCRETE BERKELEY RESEARCII REACTOR FACILIW UNIVERSITY OF CALIFORNIA AT BERKELEY l

BERKELEY, CALIFORNIA NUCLIDE RANGE OF CONCENTRATIONS (pCi/g)"

I Co 57

< 1.2 Co-60 0.4 0.4 to 2.3 1.6 l

Cs-137

<2.8 Eu 152

< 5.8 Eu 154

< 12 l

Eu 155

< 3.7 Mn 54

<2.4 I

g "Relatively high measurement sensitivities were the result of limited sample quantity.

I I

.l I

il I

45

REFERENCES 1.

Decommissionine Final Report and Termination Radiation Survey Results.

University of California at Berkelev. Berkelev Research Reactor Decommissioning Project, Biseraft Northeast Inc., April 1990.

I l

I I

I I

I I

I I

I I

46

!I

lI lI 1

I lI

!I I

APPENDIX A l

MAJOR SAMPLING AND ANAIXTICAL EQUIPMENT I

I I

I

,g I

t

I I

I I

g

l

~

APPENDIX A MAJOR SAMPLING AND ANALYrICAL EQUIPMENT j

I.

Direct Radiation Measurement Eberline PRM 6 Portable Ratemeter l

(Eberline, Santa Fe, NM)

Victorcen Nal Scintillation Detector l

Model 489 55 (Victorcen, Cleveland, OH) i Eberline " Rascal" Portable Ratemeter-Scaler g

Model PRS-1 (Eberline, Santa Fe, NM)

I Eberline Beta Gamma " Pancake" Detector Model HP 260 (Eberline, Santa Fe, NM)

I Ludlum Alpha Beta Floor Monitor Model 239-1 l

(Ludlum, Sweetwater, TX)

Ludlum Ratemeter Scaler l

Model 2221 I

(Ludlum, Sweetwater, TX)

Ludlum Alpha Beta Gas Proportional Detector Model 43-68 (Ludlum, Sweetwater, TX)

)

Reuter-Stokes Pressurized Ion Chamber Model RSS-111 Reuter Stokes, Clevelano, OH)

II.

Laboratory Analytical Equipment Low BKG Alpba Beta Counter i

Model LB 5110 j

t (Tenaelec, Oak Rige, TN)

A-1

I I

Tri-Carb Liquid Scintillation Anal.

Model 1900CA (Packard Instrument Co., Meridan, CT)

I High Purity Germanium Coaxial Well Detector Model GWL.110210-PWS S, 23% Eff.

l (EG&G ORTEC, Oak Ridge, TN)

Used in conjunction with:

l

1. cad Shield Model G 16 (Applied Physical Technology, Atlanta, GA)

High-Purity Germanium Detector Model IGC25, 25% Eff.

(Princeton Gamma Tech, Princeton, NJ)

Used in conjunction with:

I Lead Shield (Nuclear Data, Schaumburg, IL)

I Multichannel Analyzer ND66/MicroVax (Nuclear Data, Schaumburg, IIJDigital l

Equipment, Maynard, MA)

I I

I I

I lI A-2 I

lI i

i

)I

!I I

l APPENDIX B E

MEASUREMENT AND ANALYTICAL PROCEDURES

'g i

l I

f I

i g

?

I I

I l I I

I APPENDIX B MEASUREMENT AND ANALYTICAL PROCEDURES Surface Scans Surface scans were performed by passing the probes slowly over the surface; the distance between the probe and the surface was maintained at a minimum nominally about 1 cm. Identification of elevated levels was based on increases in the audible signal from the recording or indicating instrument. Scans of large surface areas of the floor of 2

the facility were accomplished by use of a gas proportional Door monitor, with a 550 cm sensitive area. The detector was slowly moved in a systematic pattern to cover 100% of the accessible areas. Other surfaces were scanned using smaller, hand held detectors.

Combinations of detectors and instruments for the scans were:

Beta-Gamma-Pancake GM probe with PRS 1 scaler /ratemeter.

g Gamma Nai scintillation detector (3.2 cm x 3.8 cm crystal) with PRM 6 ratemeter.

l Alpha Beta Gas Proportional Floor Monitor with Ludlum Model 2220 Scaler /ratemeter.

2 Alpha Beta Gas Proportional 100 cm probes with Ludlum Model 2221 Scaler /ratemeter.

I Surface ActMtv Measurements Measurements of total alpha plus beta activity levels were performed using Ludlum Model 2221 portable scaler /ratemeters with Model 43-68 hand held gas proportional 2

probes. Count rates (cpm) were converted to disintegration rates (dpm/100 cm ) by dividing the net rate by the 4 x efficiency and correcting for the active area of the 2

detector, The background count rate for the 100 cm proportional detectors averaged approximately 250 cpm; the average background count rate was approximately 40 cpm for the GM detectors, g

B1

'I

~

Removable Actkity Measurement g

Smears for determination of removable activity levels were performed using numbered filter paper disks,47 mm in diameter; smears were placed in labeled envelopes l

with the location and other pertinent information recorded. The smears were counted on a low background gas proportional counter for gross alpha and gross beta activity.

Smears were cut up and placed into scintillation vials containing a commercial

" cocktail"; vials were analyzed by liquid scintillation counting for tritium activity.

Gamma Exposure Rate Measurements I

Measurements of gamma exposure rates were performed using a Reuter Stokes pressurized ionization chamber. The chamber was placed 1 meter above the surface at I

several locations throughout the facility.

Gamma Spectrometry I

Samples were placed in an appropriate container, chosen to reproduce the calibrated counting geometry. Net weights were determined and the sampbs counted using a high purity germanium detector coupled to a Nuclear Data Model ND-66/MicroVaxIl pulse height analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the l

computer capabilities inherent in the analyzer system.

Energy peaks used for determination of radionuclides of concern were:

l Co-57 0.136 MeV Co-60 1.173 MeV Cs 137 0.661 MeV Eu 152 0.344 MeV Eu 154 0.723 MeV B2 lI

I Eu 155 0.105 hieV Mn 54 0.834 MeV g

U 238 1.00 MeV from Pa 234 U 235 0.143 MeV Th 232 0.911 MeV from Ac-228 Ra 226 0.609 MeV from Bi-214 I

t Spectra were reviewed for other identifiable photopeaks.

Uncertainties and Detection Limits The uncertainties associated with the analytical data presented in the tables of this report, represent the 95% confidence levels for that data. These uncertainties were calculated based on both the gross sample count levels and the associated background count levels. When the net samples count was less.han the 95% statistical deviation of the background count, the sample concentration was reported as less than the detection limits of the measurement procedure. Because of variations in background levels, sample volumes or weights, measurement efficiencies, and Compton contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument g'

to instrument. Additional uncertainties of + 6 to 10%, associated with sampling and laboratory procedures, have not been propagated into the data presented in this report.

Calibration and Quality Assurance The Environmental Survey and Site Assessment Program conducted the survey and analytical activities in accordance with field survey and laboratory procedures which are documented in manuals developed specifically for the Oak Ridge Associated Universities' ESSAP to meet the requirements of ANSI /ASME Nuclear Quality Assurance 1 (NOA 1).

I B-3 I

The specific manuals and procedures applicable to this survey were the " Quality Assurance Manual," February 1990, Revision 3;" Survey Procedures Manual," March 1990, Revision 5; and the " Laboratory Procedures Manual," February,1990, Revision 5.

g With the exception of the measurements conducted with portable gamma scintillation survey meters, instruments were calibrated with NIST traceable standards.

I Quality control procedures on all instruments inciaderi dahy background and check-l source measurements to confirm equipment operation within acceptable statistical fluctuations. The ORAU laboratory participates in the EPA and EML Quality Assurance l

Programs.

I I

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I B-4

,I I

-