ML20065N871

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Confirmatory Radiological Survey of Berkeley Research Reactor Facility
ML20065N871
Person / Time
Site: Berkeley Research Reactor
Issue date: 11/30/1990
From: Vitkus T
OAK RIDGE NATIONAL LABORATORY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20065N874 List:
References
ORAU-90-D-53, NUDOCS 9012120334
Download: ML20065N871 (63)
v • d • e


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NRC Inspection Report No. 50-224/90-01 l

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CONFIRMATORY RADIOLOGICAL SURVEY l "o%W. OFTHE Mf,,** BERKELEY RESEARCH REACTOR FACILITY 72., UNIVERSITY OF CALIFORNIA Rooan v one. AT BERKELEY MW Industrial and BERKELEY, CALIFORNIA -

Medical Nucosar T. J. VITKUS l g*Y mm o, Radiation Safety and Safeguards, I Emugency.

Preparedness and Radiological Pietection Branch I

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'I Erwironmental Survey and Site Assessment Program Energy / Environment Systems Divisbn FlNAL REPORT NOVEMBER 1990 I < >

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OR AU 90/K.53 CONFIRMATORY RADIOLOGICAL SURVEY OF THE BERKELEY RESEARCH REACTOR FACILITY UNIVERSITY OF CALIFORNIA AT BERKELEY BERKELEY, CALIFORNIA

.j Prepared by -

Timothy J. Vitkus Environmentr' Survey and Site Assessment Program

- Energy / Environmental Systems Division Oak Ridge Associated Universities Oak Ridge, Tennessee 37831-0117 Project Staff J. D. Berger M. A. Laudeman J. P. Evans

  • E. A. Powell L F. Friedman P. B. Slaten i

R. C. Gosslee C. F. Weaver Prepared for i

Division of Industrial and Medical Nuclear Safety and DMsion of Radiation Safety and Safeguards Emergency Preparedneu and Radiological Protection Branch U.S. Nuclear Regulatnry Commission Region V Office

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FINAL REPORT NOVEMBER 1990 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 .

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

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CONFIRMATORY RADIOLOGICAL SURWW OF THE BERKELEY RESEARCH REACTOR FACIIIIY UNIVERSTIY OF CALIFORNIA AT BERKELEY

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BERKELEY, CALIFORNIA Prepared by: Date: //!'/ [6

. T. J. Nitkus, Project 1.cader

,- Environmental Survey and Site Assessment Program M Date: //IIIb Reviewed by[:

. D. Be'rger, ggram Director Environmental Survey and Site Assessment Program Reviewed by: C E, b) MA Date: />ltl90 C. F. Weaver, Laboratory Manager

, Environmental Survey and Site Assessment Program Approved Date://!9 S R. Cloutier, Assistant Chairman Energy / Environment Systems Division

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TABLE OF CONTENTS

) PAGE

. LIST OF FIG URES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Ii

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LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv INTRODUCTION . . . . . . . . '. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 FACILITY DESCRIPTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 PR OCEDURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 a FINDINGS & RESULTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 COMPARISON OF RESUL'I3 WITH GUIDELINES . . . . . . . . . . . . . . . . . . . . 7

SUMMARY

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 APPENDICES Appendix A: Major Sampling and Analytical Equipment t

4 Appendix B: Measurement and Analytical Procedures l a e

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I LIST OF FIGURES Pl- -

} FIGURE 1: City of Berkeley, CA Showing Campus Area . . . . . . . . . . . . . . . 10-4.

FIGURE 2:- Plot Plan Showing Campus Area and Etcheverry Hall. . . . . .-. . . 11 FIGURE 3: UC Berkeley.Etcheverry Hall. . . . . . . . . . . . . . . . . . . . . . . . . . 12

p. FIGURE 4: Vertical Section Berkeley Research Reactor. . . . . . . . . . . . . . . . 13 FIGURE 5: Section Through Etcheverry Hall . . . . . . . . . . . . . . . . . . . . . . . 14 F

i FIGURE 6: UC Berkeley.Etcheverry Hall Ground Floor. Nucleonic Lab and Environs. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

... FIGURE 7: Section Through Etcheverry Hall Showing Background Exposure Rate Measurement I.ocations . . . . . . . . . . 16 FIGURE 8: UC Berkeley.Etcheverry Hall Showing Exposure Rate Measurement 1.ocations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 FIGURE 9: Room 1140, Emergency Egress, and Room 1110B Direct Measurement I.ocations and Ground Floor Exposure Rate Measurement Locations. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18

..,. FIGURE 10: Elevation North Wall, Room 1140 . . . . . . . . . . . . . . . . . . . . . . 19

' FIGURE 11: Elevation South Wall, Room 1140 ..................... 20 FIGURE 12: Elevation East Wall, Room 1140 ...................... 21 FIGURE 13: Elevation West Wall, Room 1140...... .................. 22 FIGURE 14: North Wall, Reactor Monolith Exterior. . . . . . . . . . . . . . . . . . 23 F,

1 FIGURE 15: South Wall, Reactor Monolith Exterior . . . . . . . . . . . . . . . . . . . - 24 FIGURE 161 , Operator's Platform Walking Surface . . . . . . . . . . . . . . . . . . . . 25

}.

FIGURE 17: Monolith Mezzanine . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 1

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i LIST OF FIGURES (Continued)

PAGE j FIGURE 18: Reactor Monolith Walking Surface . . . . . . . . . . . . . . . . ..v . . . . 27 FIGURE 19: Reactor Monolith Exposure Room and Pool Floor . . . . . . . . . . 28 FIGURE 20: Reactor Monolith Interior. North Wall. . . . . . . . . . . . . . . . . . . 29 FIGURE 21: Reactor Monolith Interior-South Wall . . . . . . . . . . . . . . . . . . . 30 2 FIGURE 22: Reactor Monolith Interior East Wall . . . . . . . . . . . . . . . . . . . . 31 FIGURE 23: Reactor Monolith Interior West Wall . . . . . . . . . . . . . . . . . . . 32

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, FIGURE 24: Reactor Monolith Exposure Room Ceiling. . . . . . . . . . . . . . . . 33 FIGURE 25: BRR Exposure Room Door. . . . . . . . . . . . . . . . . . . . . . . . . . 34 FIGURE 26:. BRR Thermal Column Door . . . . . . . . . . . . . . . . . . . . . . . . . . 35 FIGURE 27: Vertical Column Plug . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 36 FIGURE 28: Developed View of Storage We.Il Room 1140......,....... 37

, FIGURE 29: Reactor Operator's Office . . . . . . . . . . . . . . . . . . . . . . . . . . . 38 FIGURE 30: Decontamination Facility Floor and Walls . . . . . . . . . . . . . . . . 39 FIGURE 31: UC Berkeley-Etcheverry . Hall Showing Soil Sampling Locations . . 40 1 -

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LIST OF TABLES PAGE

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TABG 1: Exposure Rate Measurements . . . . . . . . . . . . . . . . . . . . . . . . 41 1 TABG 2: Summary of Surface Activity . . . . . . . . . . . . . . . . . . . . . . . . . 42 TABG 3: Radionuclide Concentrations in Soil . . . . . . . . . . . . . . . . . . . . 44 TABG 4: Radionuclide Concentrations in Concrete. . . . . . . . . . . . . . . . . . 45 1

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CONFIRMATORY RADIOIDGICAL SURVEY OF THE BERKELEY RESEARCH REACTOR FACILITY UNIVERSITY OF CALIFORNIA AT BERKFIIY BERKELEY, CALIFORNIA INTRODUCTION The Universiti af California at Berkeley (UCB) operated a 1 MW 'IRIGA Mark UI Reactor from August 1966 through December 1987, with a total oower output during this period of 292.5 mwd. The Berkeley Research Reactor (BRR) was located in Etcheverry Hall on the UCB campus in Berkeley, California (Figures 1 - 3). The unit was a General Atomics heterugaous pool-type reactor (Figure 4) and provided a source of ionizing 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 License No. R 101 (Docket No. 50 224).

Reactor operation actMties 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 l bay, was the result of past experimental work with tritium,and natural uranium. These

. exocriments were conducted under a California Radioactive Materials License.

l 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 l reactor components and support equipment, and scarification of activated concrete within ij the reactor _ tank.

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Once decommissioning was cornpleted, a survey of the reactor crwirons, conducted by the licensee's agent, demonstrated that the residual radiation 1:vels satisfy the established NRC guidelines. The Region V Office of the NRC requested that the Emironmental Survey and Site Assessment Program of Oak Ridge Associated Universities (ORAU) conduct a survey of the facility to confirm those findings.

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

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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.

The following areas were included as part of the ORAU survey: the high. bay reactor room (Room 1140) measuring approximately 924 m ,2 an emergency egress measuring 30 m 2, the reactor operators office (15 m 2), the personnel decontamination facility (22 m2),

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 IJcense 1333-62 includes sealed neutron sources contained in a storage well in

. Room 1140 and Room 1110B exclusive of the previously described hood.

PROCEDURES Objective On July 16 - 18, 1990 ORAU conducted a confirmatory survey of the Berkeley Research Reactor (BRR) facility. The purpose of the survey was to verify the adequacy l

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

'l Document Review -

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

' of the reactor. ,

L l Survey Procedures l~

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1. The reference grid established by the licensee was utilized by ORAU during the course 'of the survey. 'Ibe grid consisted of 1 m x 1 m blocks in areas designated as high contamination potential areas. These areas included the reactor itself and 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

.s 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 NaI(TI) gamrna scintillation detectors coupled to countrate meters with audible indicators.

- 3., Large area and/or 100 cm2 hand-held gas proportional detectors were used to scan-

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-floors, lower walls, cad equipment for alpha plus beta activity. Accessible ceilings, pipes, ducts and other overhead suw:tures were scanned with thin-window GM j detectors. All detectors were coupled to countrate meters / scalers with audible indicators.-

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4. 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). f

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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 Doors, kmer walls, and hoods (Figures 9 - 30). g Measurements were performed at the center and four points equidistant from the center and grid block corners. Gas proportional detectors for identifying alpha plus beta activity were utilized for these measurements. Single-point measurements were performed on upper walls and accessible ceilings within Room 1140, the reactor operators office, and the airlock Doors and walls using gas proportional and or GM detectors (Figures 9 - 30). All detectors were coupled to countrate meters / scalers.

During the course of the survey, the radiological condition of the facility was determined to be such that extensive upper wall and ceilhig measurements were not required. AdditionaW, 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.

6. Smear samples, for determining removable activity levels, were collected from the 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 monolith.

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FINDINGS AND RESULTS l'

'8 Surface Sm 1 Surface scans for alpha plus beta activity did not identify any areas of ele >ated contact radiation levels. Gamma scans inside Etcheverry Hall identified one location with elevated

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activity. This area was associated with a laboratory bench, situated along the north wsil

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of Room 1140. Further investigation revealed an encapsulated check. source which was removed and returned to appropriate UCB personnel; gamma radiation returned to background levels following source removal. Gamma scans of the exterior of Etcheverry Hall identified two areas of elevated activity located in the west alley adjheent to the L budding (Figure 31).

Exposure Rate Measurements

Exposure rate measurements and locations are given in Table 1. Background

, measurements were 7 gR/h to 9 gR/h at one meter above surfaces. Final exposure rate

.. measurements for the reactor facility and immediate environs ranged from 8 gR/h to

. 10 pR/h.

l Surface Activity Levels The results of total and removable surface actiity measurements are summarized in Table 2. Most of the measurements were below the lower lhits of detection for the

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

l 440 dpm/100 cm2 . Removable activity measured in grid blocks was <8 dpm/100 cm for j alpha and <}8 dpm/100 cm2for beta. Total activity levels for single point measurements 1

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were <250 to 1700 dpm/100 cm2 for alpha plus beta and <S40 dpm/100 cm2 for beta-gamma. Removable activity levels were <8 dpm/100 cm2 for alpha and <18 dpm/100 cm 2 for beta. Removable tritium activity leveh were <22 dpm/100 cm2 ta '3 dpm/100 cm2, Radionuclide Concentrations in Concrete Concentration levoh 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 2 1.6 pCi/g.

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No guideline leveh for Co-60 in building materiah have been established for this site. The crposure pathway for Co-60 is direct gamma radiation. Although there is evidence of low iesch of this activation product in the concrete, exposure rates in the facility are wel below 5 gR/h above backgruund, and therefore the measured concentrations r/ Co-60 are considered such that the basic release criteria is satisfied.

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

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

- Concentrations of radionuclides in samples collected from the alley are summarized j in Table 3. Concentrations of radionuclides in the post remediation sample are as follows

U 235, 0.5 0.2 pCi/g; U 238, 4.4 z 1.3 pCilg; Total U,17 pCi/g; Th.232,1.2

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

The radionuclides present and tleir respective concentrations, indicate that the material contains natural unprocessed uran um including daughter products. The NRC 8

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 commercial product st.ch as blasting grit and is not associated with NRC licensed activities.

The final maximum gamma exposure rate measurement for the remediated areas was 9 gR/h which is within the 7 to 9 gR/h site background levels.

COMPARISON OF RESULTS MTTH GUIDELINES 1

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 15,000 dpm/100 cm 2 (marimum in a 100 cm2 area) _

5,000 dpm/100 cm2 (averaged over 1 m2 )

1,000 dpm/100 cm8, removable j l

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Residual Beta Gamma Emitters 8

(marimum in a 100 cm2 area) 15,000 dpm/100 cm

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5,000 dpm/100 cm2 (averaged over 1 m2 )

[ 1,000 dpm/100 cm2, removable -

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All measurements conducted during this survey were well within these guideline l@veIS.

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-l The guideline for gamma exposure rate is 5 pR/h above background at 1 m from

,, surfaces. The marimum level measured in the facility was 9 gR/h; the maximum level 'l

i. . outside the facility was 10 pR/h. These levels are less than 5 R/h above_ the area .
., background level of 7 to 9 gR/h which meets the established guideline.

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SUMMARY

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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

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

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measurements, and soil and concrete sampling. The findings support the close out sun'ey performed by the licensee, and confirm that the radiological conditions of the BRR facility satisfy the NRC guidelines for release to unrestricted use.

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~ * '

6 ROOW 11108

. METERS A

15 t

1 FIGURE 9: Room 1140, Emergency Egress, and Room 11108 l Direct Measurement Locations and Ground Floor i Expesure Rote Measurement Locations 18

, QRQ21 i

3AV 3AW 5AX MY MZ 3SA 388 3G

~~

1 a

.n..

)

2

~

i 3

e 4

WEST PORDON 30 3H 31 3J 3K 3L 3W 3N r ., , .' .

1'

.!" f P . d L DUCT l

2 1

l .

! 2sP 230 2eR 2ss trT ts> a I

i l

3  :

i. 4 WIIIglllIIl lli i IIII"g -

ser tac new nat no mar int 9m taw sat. = tw ene 2nr ter ?nt 2cA 4f _ h Sh '// DQH

~

=

6k  !

~

EAST PORTION MEASUREMENT LOCATIONS r

2 GRID BLOCK 1

A SINGLE POINT JL -

- org m

- 0 10 i WETERS I ]i Elevation North Wall, Room 1140 l FIGURE 10:

I, l

19

0,RR&B 3V 3BC 300 3BE 3BF 300 3BH 3 61

' sk g AL JL DUCTWORK RK 2

1

'i I 4

WEST PORTION 3R 3S 3T 3U 3V 30 3P , 30

"" CRANE CRANE ' '

kTRACK 1 TEK 4

I 4N '

2 DUCTWORK O J 4

,' x n ece ro zr er em zw sci r; textrt eeu rw see r, re en ses ser seu sev sew _

1 h

~

2 // $

3 I I / .

EAST PORTIO" MEASUREMENT LOCATIONS l

2 GRID BLOCK A SINGLE PolNT rr jp y reti 1 3 METERS FIGURE 11: Elevation South Wall, Room 1140 i

i 20

S  !

. .hR10 1

1 l

r- M 39 3C 2AW 2AN 2A0 2AP 2AQ 2AR 2AS 30 3E 3F i 1 A l l

L WL p 2I I '

aduct l 2 3 FROW HOOD 1..

4

.. 5 j I

- 3 exhaust 6 l O CT _ .

h 2AE 2Ar 2*G 2AH 2Al 2AJ 2AK 2.1 2AT 2AU 2AV 2AW 2AX 2AY 2AZ 8

9 ,

l 10 l.

4 MEASUREMENT

. LOCATIONS A SINGLE POINT 1 _

3 7

0 10 I .

METERS p

L1 -

l1 FIGURE 12: Elevation East Wall, Room 1140 i

l 21 l

l l

'8RR11 ,

+

1 ,

L1 I,

3BJ 3BK 3pL 39W. 39N 390 JBP 380 1 A A

  • A DOCTWORK 40 N

3 A N A xu msmc .

/

a. 42

', 3

!a

. MEASUREMENT LOCATIONS

] ORID BLOCK A $1NCLE PolNT

+ =

N 4=n a to

"="'

1- -

] FIGURE 13: Elevation West Woll, Room 1140 i

22

_.___,.m.,_ . - _ . _ , . _ _ _ , _ . , . _ . _ _ , , , _ , . . , . . . . . . . _ . _ . _ , _ , _ _ . , . . , . . _ ,

s BRR5 s

e 1

1 2P 20 2H 25 A 21 ZU ZV 2W ZK 2Y 2L Z4A ZLU 2AC 2AD m 1 I I

e 6" P!PL - -

c.Ectme f 3 PANEL a  %

K m

w y _._ i 3

P

  • f-

,f A s 1 7 t-r l a

MEASUREMENT LOCATIONS A SINGLE PotNT

~

z  %- w 9

  • 10 f - 6 METERS s

1 FIGURE 14: North Well, Reactor Monolith Exterior l

23

BRC6 1

1

~

= 2A 2 d 2C ZU 2L ZF 25 ZH Zi 2J 2K 2L iW kN 2 C.

I JL

' A I 6* PIPE 3\

., s 2 l 1

3" -

4 5

't 6 4 7 s

o MEASUREMENT LOCATIONS A SWGLE PONT 1

T ~

0 10 METERS 1 _.

1 FIGURE 15: South Wall Reactor, Monolith Exterior 24

e,hns 1

2HQ 2HR 2KS 2HT 2hu 2W 1

2 j 3

MEASUREMENT LOCATIONS

]CRIDDLOCK A SINGLE PolNT w: @ m 0 10 M

ME1 1

FIGURE 16: Operator's Platform Walking Surface 25

SRR$

e 1

1 2GU 2CV 20W 2GX 20Y 2GZ 2HA 2HB

- ~

1

/  %

1

/  %

... 2 3 ) N. (

\4:.:. .: . :. :%. .. N

/ . . .. :

\

4

/

/N .

, 3 f.:j::.::::: 'l

' .:::i:.\ .

(

r. .. ... .. .. . . . .....\ .. \

y p::::1.::::: l

. s\

.. .:::':'::3:

1 . . . . :. .. .:.

- 4:: ..:.: .  :. ': -

/ f. ::.,:.:.:.:.::.:.:::

8

...::..:..:::.:.::\:

. , , , ,;...%'.5..%:'

. . .. ' MEASUREMENT LOCATIONS

  • GRID BLOCK A SINGLE POINT

~

- 1,r - g-P FEET l

10 METERS 1

FIGURE 17: Monolith Mezzanine i

i.

26 i

B,hR7 4

1AU 1AV 1AW iAX 1AY 1A2 iBA 189 fBC

  1. I'  %

I =

1

__p 2 l l i

/

I l k o T

/

> h s

I

/ \

\

M

///.

1 -

\ / \ _

/

t 7 i

9 I lo --

7 11 ,_

'- MEASUREMENT l q j _n LOCATIONS l 12 GRID BLOCK

'3

! l A $1NGLE PolNT I"

I __ z 4=x

! 10 O

is L __ ____ __ J f------  ;

I FIGURE 18: Reactor Monolith Walking Surface 27

e SRR17 o

4 1  :

L 1

F d

t t

..?......

.*'.J

.'/:'...3...lg'..'..................*

.., :.g, ..:.. ;, .. '.. ....'. ' ; .. e.. ,..'.. ..w......i'. ., .i..'.'. , ...V,;.l..'.

. . . . . . . .jp * *)'s.

y . ' *,..,' * .s. ..,.p.s.

.... .;., .>' .. .e...

    • . .. ...g......'.

. . .;... ;.. .,. s.

s,

. ...'.t. .; . . ..;...;.+.,....,.

+ ..e. . .. ' f .

..'..,e'.. . ., ,. .... ..

J.e *.

t. 's...?.'. . , ,. ; . . , ,

.; . ?.. g. .* .. c.c.'. ; .. , . ..

er a-

  • .................;t.,.

..;..,e.' .. . . . .

.a .s.. ..*v<,. . v. .... ..

j .. , ..s.. .. s.;3 ...,..e...',.e....

......,..,.;..;..v....

v. ..e.............s.;.....

s.. . . . ., . . ; '

, f..) ..s.,..,..;...

. te

.. ..,.'s.

. .. ... '.. .s.. .;. .. ,. ,t.

.. .. . 4.

. ..s.'.;. .. ... .; . .. ,r. .. . .

.,...,.,.a...;....'

..,....,.e........ ....e...:.....

.,. g v . ., . , g.. . .. ...

..s. . . . . ,. . . .v

. . . ; . . t.

  • g. .. ., ... . . . .

' * + . ..f'. . $

. v,..s . ; .. ,

.; .;. .' .g . ,;.

v., .7;. . , . . r '/.,.*,;.'...

. . ... ... .., 'f.. . ....,... ' ., . . .e. . f. 7. ..'.....'; . .. . ........., .. . . ..

I..........

+

( 't ..e . . ; . . ;. ,

. ' .; '. . '. ,c

.. .. . .. . .'. . e . j.. . . ; . .

<.....s.

........e.........s...

.., .. .. . .c... . ...<......4.... . . . . . . . . i............ ..

...<.; ... .e, , . .. ... . . . . . .

..:.::::.:(..:::.kk dl.'h';;s's .}I.'!\. .... ..

A N l MEASUREMENT

.. . . s. . . .

. :.. : . . ... ... .c.1.$..{., f'-~..' . .y. )..s.

I'!

.s:: $'h , c.::.'

LOCATl0NS

~........s. p g

a CRID BLOCK A SiNOLE PONT L -

x-3 v.-

FEET 3

WETERS I FIGURE 19: Reactor Monolith Exposure Roorn

! and Pool Floor i

-f 28

.- ._ _ . ~ . . . . . - .,_ .. _._.-.- _. . .-. . -.- .a -

t BSR15 4

i n

s

! 1H 11 iJ ik it iV 1N 10 I .... f

\  :..?

r ,......,...,.,

.;.'.;.;. .,g g .

n

- f" .........,,.,

I 1

2. ..g

( . l..

p...:.,y.q.......

4  !
:.::::q...y-

': . .g:

. .s t.. ..... ... .. y..

5 --'

g fj F_

p.;

8 i / .

msH nDOR .p  ;

.....\

.....'*......'*..w........

. . . ....*..,.........=.............%.... __

y

,f LR -l

,. ... .. .w... ... .,..*.

i l

MEASUREMENT LOCATIONS GRID BLOCK A SINGLE POINT 1 -

r5 FEET C 10 VM 0 3 WETERS l

FIGURE 20: Reactor Monolith Interior-North Wall 29

ettQ13 i

= 1 1

l l

4

(

i

'l tr 1Y 17 1AA 145 140 180 1Af  ! 1

' (

' /

. . . .,. . . ,. . . / )

... J

...... l

... ... .... .......... .... .. .... ...... .:. ..5.... .... ...... ... ...... ...<. . . . . . . . .

. . . .V. ..n . .iy;:.:.g;....

. . . .:.................. . .; :.-u1 1,a w

.:.::u. . .. 0:.,, ..

s\ j 4;? '.;:

'.: ':...:e ' ':.

.f
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.;. .

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p ,

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/)

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nmsn noon I; /

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..;..d.. . . .. ::. . .. :. . . . . :m. . . . .. .

3. .: x. . .. .... .... ....,, .. ... ,.. ..,. .. :.. .w.r.

. . . ..g ..;. . .g..;q.

....g....................

.:.. . ' . . . ..... ; . .. . .:.1 MEASUREMENT LOCATIONS I

3 ] CRID BLOCK A SINGLE POINT JL -

TF FILT 10 WETERS i

l I

l- FIGURE 21: Reactor Monolith Interior-South Wall l

30 i-I .-

.. s+ -w.. < ._, -

, , . . - , - - - _,,-..-.--...-..-.-..--~#, _ . - - - . - , - - , . . , - ~ . _..----.-,-,-.,,.,4,.,, - , , - i . . - - . . _ , , 4.m--., me.

(DR16

=

ll!ll I  !  !  ! ! I.I I f us

'/l l " E, -

3 1LJJL '*_ .

I '3 ff/ f/f Fx i

. f//

. <j,7 <

{

1 russ rtooR

' VL'wll $

MEASUREMENT LOCATIONS GRID BLOCK A siNGLL POINT N i FEET 0 10 METERS FIGURE 22: Reactor Monolith Interior-East Wall 31

R019 g ...

4 I

1 an a m .

(- ',..,...;..

.. ..:.. ._s'.. c. . .;

f/ 1.

h:.

.. :.:.;. ' :.f l

. :::.:.:.:t

~

c

, );.: .:.. . . .' :.

I  :....

l Yb .,?

. . ;. .. ..;p,

. .l

' ' :.f

, y:. - nmsn rtoon

i. MEASUREMENT LOCATIONS

] GRID DLOCK A SINGLE PolNT

\ -- .x y y-r Q -

10 6 3 METERS 1 -

~1 FIGURE 23: Reactor Monolith Interior-West Wall l

l 32

BM20 f 5

. . . .......;
. .s ..:.us ao . .s 1.a. . ..... . . . . . . . .w w

. . .ar :..

. . . .. ~ n .

, ., , , ..... ., . .;g.9 ,

.......,,,. r .

. . . . . . . . . . l.;f..

. . .;,- l. l '. . ' ;. .. p.,

. ; . .,:.:'::..:.:i,:l.

. .. .. .. .. ... .. . , \

.l.

, .. .l.;. . .g'., .

.. .;. .. .. .,.. ,. l:. . - .

c 1- 21_;

I I

8 MEASUREMENT LOCATIONS l ] GRID BLOCK A SINCLI POINT

= 4-->

ar -N Q 10 b 5 WETERS FIGURE 24: Reactor Monolith Exposure Room Ceiling 33

ORR14

=

1 2

3

> 3 2GF 2GJ i i 4

l

/ //

l

  • l u 5

.- , /. .

/

FINISH FLOOR / // q 6

/ /

MEASUREMENT LOCATIONS

] GRID BLOCK A SINGLE POINT wdfnt 0 ,10 6

uM $

FIGURE 25: BRR Exposure Room Door 1

34

, . . . . -.. ... . . . - .~. . -.

4 BBR12 2.(

C 2GK 2GL 2GM 2GN 2GO 2GP 200 l I

(

1 \

2 l l

3 1

t. I I ll l I ll l

5 1

l MEASUPEMENT LOCAVONS

,t CRIO BLOCK A SINGLE POINT C C I

Li 7-0 10 l- utrERS e

I FIGURE 26: BRR Thermal Columr. soor 35

BER13 idi 1

2GR 2GT 2

f// o 3

1 4

MEASUREMENT

-l LOCATIONS GRID BLOCK I ' A - SINGLE P0 TNT

' = Q=s 0 10

. wcTras

. FIGURE 27: Vertical Thermal Column Plug 36

BER28 4

2 2BA 2BB 200 200 2BE i i N A /

I I 1

l 2

1 3

4 4

r MEASUREMENT i

5 [ g LOCATIONS

( / A SINGLE POINT J N_x,e 0 10

$ s METERS FIGURE 28: Developed View of Storage Well Room 1140 37

r BkR2O 2EH 2D 2EJ 2EK 2D. 2EM ll

, i 1

i 2

wer 3 TANK 4

1 l

i I MEASUR". MENT i

LOCAh0NS CRID BLOCK

. f- n A SINGLE POINT f,

l- Nch t

' O 10 3

METERS FIGURE 29: Reactor Operator's Office 38

A BRR85 A

t

.~

2FL 2FW 2FN 2F0 2FP2F02FR 2FS 2FT 2FU 2FV 2FW 2FX 2FY 2FZ2GA2GB 200 200 2GE 1

2 0 / f WALL 2GF 200 20H 2Gi 2GJ 2GK 20L 20W 20N 200 2GP 200 20R 205 1

i

'2 j 3

WN.L 2EN 2E0 2EP 2EQ 2ER 2ES I i 1

r t 1

MEASUREMENT

.j 3 -

c.1 c- LOCATIONS

~

4 /

'/ , 2 cRIO BLOCK FLOOR Ng h =

10 NETERS l

1, FIGURE 30: Decontamination Facility Floor and Walls l 39

,BRR3o

< v

~r'D D E J'o oIO~ {

l ] Dr .0 0 E l -

] ] _

E. 0 ] j l

_9 ] C J q r

. =

+

l

=]=- . .

Cl g 1

-1

, ma:

  • + *

]l k

= . . ... =m _

w

! O

\

00 00 d0 0 000[ l ETCHEVERRY HALL f

{j

{.-] _

SOIL SAMPLING

-I 4E LOCATIONS f

AREAS OF ELEVATED CONTACT RADIATION N=h t 0 40 2

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

TABLE 1 EXPOSURE RATE MFASUREMENTS i

BERKELEY RESEARCH REACTOR FACILITY UNIVERSITY OF CALIFORNIA AT BERKELEY ~

BERKELEY, CALIFORNIA -

Exposure Rate (pR/h)

Location at 1 m Above Surface t

Background Measurements Exteriof North Etcheverrey Hall 8 Exteriof East Etcheverrey Hall 9 Exterior South Etcheverrey Hall 7 Exterior

  • West Alley Etcheverrey Hall 8 Interior
  • Third Floor Lobby. 8 Interior
  • Fifth Floor / Center of East Corridor 8 Interi.n* Fifth Floor / South End of East Corridor 9 Intrefor6 Sixth Floor / Center of East Corridor 8 JLterior* Sixth Floor / South End Eet Couicor 9 Reactor Facility & Elevated location Measurements Exterior" West Alley Etcheverrey Hall 12 Exterior
  • West Alley Etcheverrey Hall 10 Exterior'd West Alley Etcheverrey Hall 9 Interiof Reactor Monolith 10

, Interiof Reactor Bay (Room 1140) 9 Interiof Reactor Operators Office 9 Interiof Airlock 9 Interiof Personnel Decontamination Room 8

" Refer to Figure 8.

  • Refer to Figure 7.

Pefer to Figure 9.

  1. Measurement taken following remediation.

41

TABLE 2

~ '

SUMMARY

OF SURFACE Act1VIW BERKELEY RESEARCH REACTOR FACIIIIT UNIVERSTIY OF CALIFORNIA AT BERKELEY BERKELEY, CALIFORNIA Removable AdMtv Trtium Hlahest Grid Bhek Avn. Total ActWr -

(dpm/100 cnd (dpm/100 cm') (Removable)

  1. Meastred (dpm/100 cm3 (dpm/100 cm3 Alpha plus Beta Alpha @p Beta Range Alphe Range Bets Range Room Lin,ekai Lc ak-w 1140 Lower Walls <8 <18 <22 14 <240 <240 - 280 and Floor Upper Walls & <8 <18 -

45 N/A <840 Celling Equipment & <8 <18 <22 - 43 5 N/A <840 Drains Reactor Walls and <8 <18 <22 27 440 <240 - 660 M Pool & Floor Exposure <8 <18 <22

<250 <250 Room Celling i

<8 <18 <22 4 <250 <250 - 610 Exposure Door Room 1700 Door Single Point i N/A Personnel Walls and <240 <8 <18 <22 Decon Floor 1 <240 Lower Walls II <22 Reactor <250 <8 <18 Operators and Floors 1 <250 Offsce Upper Wa!!s <270 <8 <18 -

and Ceilings 1 l

TABLE 2 (Continued) ,

~

SUMMARY

OF SURFACE ACITVrIY BERKELEY RESEARCH REACIOR FACIIIIY UNIVERSITY OF CALIFORNIA AT BERKELEY BERKELEY, CALIFORNIA Hlahest Grid Block Ava. Total ActMtv Removable ActMtv Tresum

  1. Measured (dpm/100 cnd (dpm/100 cnd (dpm/100 cn@ (Removable)

Room Location t.ocations Alpha plus Beta Alpha plus Beta Range Alpha Range Beta Rsmge (dpm/100 cnd Airlock Wars and

& Hall Floor 4 - <250 <8 <18 -

To Reactor Room Vertical Walls lhermal 1 <250 <250 <8 <18 <22 Column O Horizontal Thermal Door 2 <250 <250 - 420 <8 <18 <22 Column Door Eiwengen cy Walls and 1 <240 <240 <8 <18 <22 '

Egress Floor 1110B Hood 1 <250 <250 <8 <18 <22 Storm &

II Sanitary Sewers 2 - -

<8 <18 <22

. . .. .- = . . _ .- -. -. - . .- . _

s TABLE 3 RADIONUCLIDE CONCENTRATIONS IN SOIL BERKELEY RESEARCH REACTOR FACILITY UNIVERSITY OF CAIRORNIA AT BERKELEY BERKELEY, CALIFORNIA I Sample Radionuclide Concentration (oCiM location' U-235 U-238 Total U' Th.232 Ra.226 I 2.9 2 0.4d 77 m 12 138 12 2 0.3 73 1 2 1.3

  • 0.3 36 2 10 63 4.92 0.2 30 0.3 3 0.1
  • 0.1 2.7
  • 1,7 5.3 1.0 0.5 0.9 0.2 46 Post 0.5 0.2 4.4 2 1.3 17 1.2 0.4 3.8 0.4 Remediation
  • Refer to Figure 31 for sample points.
  • Sample collected from area with highest contact gamma radiation level following excavation.

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

tncertainties represent the 95% con 5dence level, based only on counting statistics; additional laboratory uncertainties of 2 6 to.10% have not been propagated into these data.

l' L

l l

I 44 L

1

~

TABLE 4 RADIONUCLIDE CONCENTRATIONS IN CONCRETE  ;

BERKELEY RESEARCH REACTOR FACIIIn' UNIVERSITY OF CALIFORNIA AT BERKELEY BERKELEY, CALIFORNIA _~

NUCLIDE RANGE OF CONCENTRATIONS (pCi/g)*

Co-57 <1.2

! Co-60 0.4 0.4 to 2.3 1.6 i-Cs-137 <2.8 4

l Eu-152 < 5.8 i

Ee-154 < 12 ,

i Eu-155 <3.7 Mn-S4 <2.4 I

l "RelativeJy high measurement sensitivities were the resuit of limited sample quantity.

l 45

REFERENCES

1. Decommksioninn Final Reoort and Termination' Radiation Survey Results.

University of California at Berkelev. Berkelev Research Reactor Decommissionine Proiect. Biscraft Northeast Inc., April 1990.

C

O .

1 i

l l

l I

l l

l I

l APPENDIX A l

MAJOR SAMPLING AND ANC."nCAL EQUIPMENT 1

APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT L Dimet Radiation Measurement -

Eberline PRM-6 Portable Ratemeter (Eberline, Santa Fe, NM)

Victorcen Na1 Scintillation Detector Model 489-55 (Victoreen, Oeveland, OH)

Eberline Rascal" Portable Ratemeter-Scaler Model PRS-1 (Eberline, Santa Fe, NM)

Eberline Beta-Gamma " Pancake" Detector

'Model HP-260 (Eberline, Santa Fe, NM)

Ludlum Alpha Beta Floor Monitor Model 239-1 (im alum Sweetwater, TX)

Ludlum Ratemeter-Scaler Model 2221 (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, Ceveland, OH)

IL laboratory Analytical Equipment low BKG Alpha-Beta Counter Model LB-5110 (Tennelec, Oak Ridge, TN)

A-1

Tri.Carb Uquid Scintillation Anal.

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

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

(EG&G ORTEC, Oak Ridge, TN)  :

Used in conjunction with:

Lead Shield Model G 16 (Applied Physical Technology, Atlanta, GA)

High-Purity Germanium Detector Model IOC25, 25% Eff.

(Princeton Gamma-Tech, Princeton, NJ)

Used in conjunction with:

lead Shield (Nuclear Data, Schaumburg, IL)

Multichannel Analyzer ND66/MicroVax (Nuclear Data, Schaumburg, II./ Digital Equipment, Maynard, MA) l 1

4 1

1 A2 l

1 i

i i

APPDVDIX B l

l MEASUREMENT AND ANALYTICAL PROCEDURES I 1

l I

l l

l t

l l -- _._ -_- - ____ _ ___---_--____ - __-.--.

1 O

APPENDIX B MEASUREMENT AND ANALITICAL PROCEDURES Surface Scans Surface scans were performed by passing the probes slowly over thhsurface; the distance between the probe and the surface was maintained at a minimum - nominally about I 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.

Gamma - Na1 scintillation detector (3.2 cm x 3.8 cm crystal) with PRM-6 ratemeter.

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

Alpha-Beta - Gas Proportional 100 cm2 probes with Ludlum Model 2221 Scaler /ratemeter.

Surface Activity Measurements i

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 r efficiency and correcting for the active area of the detec:or. The background count rate for the 100 cm 2proportional detectors averaged apprnvimately 250 cpm; the average background count rate was approximately 40 cpm for the GM detectors.

1 B-1

v.'

' Removable Activity Measurement Smears for determination of removable activity levels were performed using numbered filter paper disks,47 mm in diameter; smears were placed in labeled envelopes with the location and other pertinent information recorded. The smears weiz counted on a low background gas proportional counter for gross alpha and gross beta aethity.

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

" cocktail"; vials were analyzed by liquid scintillation counting for tritium activity, i Gamma Ernosure Rate Measurements Measurements of gamma exposure rates were performed using a Reuter Stokes pressurized ionization chamber. The chamber was placed 1 meter above the surface at several locations throughout the facility.

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

!- computer capabilities inherent in the analyzer system. Energy peaks used for determination of radionuclides of concern were:

Co.57 0.136 MeV l Co-60 1.173 MeV Ca 137 0.661 MeV l Eu-152 0.344 MeV Eu-154 0.723 MeV B-2

Eu 155 0.105 MeV Mn 54 0.834 MeV 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 Spectra were reviewed for other identifiable photopeaks.

Uncertainties and Detection Umits 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 than 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 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 Ouality 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).

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

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

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

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