ML20147H067
| ML20147H067 | |
| Person / Time | |
|---|---|
| Site: | 07000734 |
| Issue date: | 02/26/1988 |
| From: | Jonathan Montgomery, Skov D, Thomas R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20147H048 | List: |
| References | |
| 70-0734-87-15, 70-734-87-15, NUDOCS 8803080380 | |
| Download: ML20147H067 (14) | |
Text
,
U. S. NUCLEAR REGULATORY COMISSION e
REGION V 4
Report _No. 70-734/87-15 Docket No.70-734 License No. SNM-696 Safeguards Group I.
- Licensee: GA Technologies, Inc.
P.O. Box 8S608 San Diego, California 92138 Facility Name:. Science Laboratories Building (Building 2)
Inspection at: Same e
Inspection Conducted: December 14 through_16, 1987 In pectors:-
M/
2b R. D. Thomas Chief Date Signed Nuclear Materials Safety Section
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D. D. Skov, Radiation Specialist Da~te Signed Approved by: Q W
6 4 ff N. L. Montgo%ry, Ch$f.
Date/ Signed Nuclear Materials Safety and Safeguards Branch Sumary:
Inspection on December 14-16, 1987 (Report No. 70-734/87-15)
A decontamination confirmatory survey was conducted by NRC inspectors of the portions of the Science Laboratories Building (Building 2) in which NRC
- licensed activities had been conducted. The survey results indicate that the NRC licensed portions have been satisfactorily decontaminated by the licensee.
The areas examined under the confirmatory survey are acceptable for release to unrestricted use.
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DETAILS P
1.
Persons Contacted Keith Asmussen, Manager, Licensing and Nuclear Compliance Laura Quintana, Manager, Health Physics Steve Perelman, Staff Health Physics Technician Robert Dalry, Director Facilities Keith Johnson, Manager, Facilities Engineering Harry Lomax, Construction Planner 2.
Introduction In a-letter and accompanying report to NRC Region V dated November 18, 1987, GA. Technologies ~Inc. requested an NRC confirmatory survey of several laboratories within the Laboratory B section of the Science Laboratories Building (Building 2 or "L" Building). The licensee's final report, "Decontamination of Selected GA Technologies' Science Laboratories for Release to Unrestricted Use", indicated that twenty laboratories within the building had been surveyed, and the building decontaminated to levels below the limits required for release to unrestricted use.
On December _10,1987,-the licensee reported by phone that additional areas within Building 2, which had not been included in the GA report, had also been decontaminated and were acceptable for release to unrestricted use. The additional areas identified included four laboratories within Laboratory Sections A and B, and two locations inside the Laboratory Section C service corridor The licensee's decontamination activities with respect to the additional laboratory and service corridor areas were described in the revised GA Technologies' decontamination report to the NRC dated January 18, 1988.
Activities conducted within the various laboratnries of Building 2 were authorized by NRC'and California State licenses. The confirmatory survey, conducted during the period of December 14 thru 16, 1987, included all Building 2 laboratory areas referenced in the licensee reports.
Inspectors from the State of California also performed a confirmatory survey of Building 2 beginning December 17, 1987. The State of California plans to release the Building 2 lataratory areas checked pending the results of the combined confirmatory surveys. The Building 2 i
complex is shown in Figure 1.
3.
Procedure Radiation surveys were conducted in the following laboratories of f
Building 2, which the licensee had identified for release to unrestricted use (see Figures 2 thru 4) t Section A Laboratories: 641, 643 l
F i
1
4 Section B Laboratories: 102, 104, 107, 109, 111, 113, 115, 117, 119, 122, 128, 130, 132, 134, 137, 139, 141, 143, 145, 147, 149, 151, 154 Several of the laboratories with separate room numbers identified above-were combined into one larger room.
Some laboratories also contained an upper level. mezzanine which had been occupied previously as either office space or as an additional laboratory area for the use of licensed material. At the time of the confirmatory survey, Rooms 147, 149, 151, and 154 had been released to unrestricted use and were occupied by rental tenants. With the exception of Room 104, all of the remaining rooms included in the confirmatory survey had been vacated by licensee personnel. Most rooms were empty except for such items as laboratory work benches, wall cabinets, fume hoods (Rooms 113,122,130-134,143),
drain pipes and ventilation ducts.
Gama surveys were conducted in the laboratory rooms over nearly all accessible floor areas, including the mezzanine levels. Additional floor scans were also made along the entire hallway providing direct access to the laboratories which were surveyed within Section B of Building 2.
The floor scan included one area of Room 141 where concrete had been scabbled by the licensee to remove surface contamination. All gama scans were made one to two inches above the floor surfaces.with Eberline PRM-7 survey meter Serial Numbers 247 and 510, which had been calibrated on 7/21/87 and 7/23/87 respectively.
Selected locations within the various laboratories were also surveyed using Eberline E-520 portable survey meters, Serial Numbers 2120 and 1586, which were calibrated on 10/8/87 and 11/11/87 respectively. The Eberline E-520 instruments, equipped with Model HP-260 pancake GM detectors, were used to define beta-gamma contamination levels.
Twenty-five wipe samples were also collected and analyzed for alpha and i
beta-gama radioactivity (Table 1). The wipe samples were counted in the NRC Region V Tennelec Model LB5100 Low Background System.
Confinnatory decontamination surveys were also conducted in two areas within the Laboratory Section C service corridor. The licensea had dug a pit about four feet in depth and had scabbled concrete nearby to remove a
soil and surface contamination from the service area behind Laboratory Room 331. A similar size pit was also observed in the service area behind Laboratory Room 359/361 where the licensee had removed a contaminated floor drain, concrete and soil.
Three soil samples were collected by the inspectors from the two service corridor areas. These samples were anal Environmental Sciences Laboratory (RESL)yzed at the Radiological and of the U.S. Department of Energy, Idaho Operations Office (see Tables 2 thru 4).
The Region V office received the results of the soil sample analysis on February 4, l
1988.
i l
7
):
4.
Discussion and Findings Radiation level and contamination surveys indicated the presence of radioactive contamination in four laboratories.
In Room 113, an area of less than 15 cm2 on the inside of a bench drawer had a bett-gama contamination level of approximately 33,000 dpm. Also, a small spot on a lead brick left in the same room had beta-gama contamination of approximately 80,000 dpm. Low level removable beta-gama contamination was measured from the wipes of both drawer and lead brick. -Both the drawer and lead brick were removed by the licensee for disposal.
Beta-gama radiation levels of up to 6600 dpm were measured from a wall section and adjoining floor covering an area of approximately one to two square feet in Room 128. The wall section and portions of the adjacent floor (tiles and concrete) were removed by the licensee. A resurvey of the wall and floor areas showed the removal of all radioactive contamination.
A small spot of beta-gama contamination measuring up to 11,500 dpm was also measured on a shelf in a cabinet beneath the fume hood in Room 143.
The shelf was removed by the licensee for disposal. Removable beta-gama contamination of 128 dpm was also measured on the countertop inside the same fume hood; however the contamination level is well below the limit for release to an unrestricted area under NRC guidelines.
The counter top of one bench cabinet on the mezzanine level of Room 641/643 had fixed beta-gama contamination measuring approximately 100,000 dpm over an area of less than 100 cm2 Much lower contamination levels covering about 15 cmr were measured on a small diameter pipe and floor tile behind the cabinet. The pipe section was decontaminated, and the floor tile and portions of the wood bench top were removed by the licensee for disposal. A resurvey of the above areas showed that the contamination had been removed.
Analyses of the soil samples collected from the two service corridor areas indicated that uranium-235 contamination was not detectable.
5.
Conclusions The portions of the Science Laboratory Building which were included in the confirmatory survey had been satisfactorily decorataminated by the licensee and are acceptable for release to unrestricted use in accordance with NRC guidelines.
0 TABLE 1 Wipe Contamination Survey-Wipe No.
Description of Location Results in dpm per 100 cm2 Alpha Beta-Gama 1
Room 113 - Inside top left drawer of bench cabinet 0
89 2
Room 113 - Lead brick 4
582 3
Room 113 - Hot sink drain 0
5 4
Room 113 - Drain pipe adjacent to fume hood 1
3 5
Room 113 - Inside doorknob of room door 0
4 6
Room 115 - Cabinet benchtop 0
2 7
Room 115 - Handrail in stairway 0
2 8
Room 119 - Sink facet handle 1
1 9
Room 119 - Concrete tabletop 0
2 10 Room 122 - Sink drain 1
3 11 Room 122 - Countertop inside fume hood 1
8 12 Room 122 - Doorknob between rooms 119-122 0
0 13 Room 128 - Wall behind refrigerator (after decontamination) 0 1
14 Room 128 - Floor behind refrigerator (afterdecontamination) 66 32 15 Room 134 - Sink (ground level) 1 2
16 Room 134 - Fumehood (ground level) 0 8
17 Room 134 - Sink (mezzanine) 0 1
18 Room 134 - Countert p of bench (nezzanine) 0 1
19 Room 143 - Bottom shelf inside fume hood cabinet 1
21 20 Room 143 - Countertop inside fume hood 1
128 l
.o.
TABLE-1
~
Wipe' Contamination Survey-Wipe No.
Description of Location -
Results in dpm per 100 cmt Alpha Beta-Gamma-21 Room 641 - Wall: ventilation duct
-0 0
22 Room 641-Benchtop-(mezzanine)before decontamination 15 46 4
23 Room 641-Benchtop(mezzanine)after decontamination 0
3
.24 Room 641 - Sink 3
2 25 Room 641 - Pipe outer surface behind bench (mezzanine) after decontamination 0
O' 4
_, ~ _ - _ _ _ _ _ _ _ _ _ _ - _ - _
Table 2 UNITED STATES DEPARTMENT CF ENERGY IDAHO OPERATIONS OFFICE:
RADIOLOGICAL AND ENVIRONMENTAL SCIENCES LABORATORY SAMPLE RECORD SHEET SERIAL NO.
14387A RECElVED NRCS l'C eeee**********************
ret Wy
- NRC MOD NO. ??????
- INPLANT DATE NEEDED 01/11/88 M -4 A 'O 7 l NONROUTINE SAMPLE DATE 12/14/87 SAMPLE SENT 12/21/87 ANALYZED BY: J.S.MORTON, S.GIMPEL SAMPLE HOUR 1200 MST SAMPLE RECEIVED 12/29/87 -
ORGANIZATION NRC5 HARDCOPY PRINTOUT 01/20/88 ORIGINAL SIGNED BY:
D.B.
MARTIN COMMENTS:
NRC; COLLECTED BY D.D.
SKOV; GA TECHNOLOGIES; SOIL FROM AN OPEN PIT, SERVICE CORRIDOR TO RM 359; (URANIUM BY GAMMA SCAN)
COLLECTION DATE:
12/14/87 ANALYSIS DATE:
01/06/88 DECAY TIME 23.9 DAYS
- l COUNT TIME 60 MIN.
DETECTOR NUMBER 6
SAMPLE SIZE 2.81E+02 g i
I TOTAL GROSS BKGD MINOR NET ISOTOPE RESULTS +/- IS;O**
COUNT COUNT COUNT COUNT COUNT C/M C/M C/M C/M uCi/ gram
-4
-0.07
-0.07 Co 60
( -3 +/-
4; 4 ) E -8 18 0.30 0.30 CsD137
(
9 +/-
4; 4 )E -8 281 4.68 0.12 4.56 K 40
( 2.23 +/- 0.15;0.17 !E -5
-4
-0.07
-0.07 PaM234
( -3 +/-
6; 6 )E -6.
54 0.90 0.24 0.42 0.24 U 235
(
3 +/-
6; 6 )E -8
- DECAY CORRECTION OF NATURAL CHAIN DAUGHTERS PER LONGEST LIVED PARENT
- ESTIMATED RANDOM UNCERTAINTY REPORTED IS ONE STANDARD DEVIATION, IS.
SMALL NEGATIVE AND OTHER RESULTS LESS THAN OR EQUAL TO 25 ARE INTERPRETED BY RESL AS INCLUDING "ZERO" OR AS NOT DETECTED.
FOR RESULTS GREATER THAN 2S BUT LESS THAN OR EQUAL'TO 3S, DETECTION IS QUESTIONABLE.
RESULTS GREATER THAN 3S INDICATE DETECTION.
O IS-THE ESTIMATED OVERALL UNCERTAINTY.
l
,n
-7 w-
-.y.
Tabl e 3 -
l UNITED STATES DEPARTMENT OF ENERGY IDAHO OPERATIONS OFFICE 4
RADIOLOGICAL AND ENVIRONMENTAL SCIENCES LABORATORY SAMPLE RECORD SHEET
. SERIAL.NO.-
143878 NRCS oooo**********************
l
- NRC MOD NO. ????'r?
i
- INPLANT DATE NEEDED 01/11/88 i
NONROUTINE l
SAMPLE DATE 12/14/87 SAMPLE SENT 12/21/87 ANALYZED BY: J.S.MORTON, S.GIMPEL' SAMPLE HOUR 1200 MST SAMPLE RECEIVED 12/29/87 ORGANIZATION NRCS HARDCOPY PRINTOUT 01/20/88 ORIGINAL SIGNED BY: D.B. MARTIN COMMENTS:
i NRC; COLLECTED BY D.D.
SKOV; GA TECHNOLOGIES; SOIL FROM AN OPEN PIT, SERVICE CORRIDOR TO RM 331; (URANIUM BY GAMMA SCAN)
COLLECTION DATE:
12/14/87 ANALYSIS DATE:
01/06/88 DECAY TIME 25.0 DAYS
- COUNT TIME 60 MIN.
DETECTOR NUMBER 6
SAMPLE SIZE 2.92E+02 g 4
TOTAL GROSS BKGD MINOR NET ISOTOPE RESULTS +/- IS;O**
COUNT COUNT COUNT COUNT COUNT j
C/M C/M C/M C/M uCi/ gram i
3 0.05 0.05 Co 60
(
2 +/-
4; 4 )E -8 0
0.00 0.00 CsD137
(
0 +/-
3; 3 )E -8 294 4.90 0.12 4.78 K 40
( 2.27 +/- 0.15;0.17 )E -5 1
0.02 0.02 PaM234
(
1 +/-
4; 4 ) E -6 25 0.42 0.24 0.30
-0.12 U 235
( -2 +/-
6; 6 )E -8 i
- DECAY CORRECTION OF NATURAL CHAIN DAUGHTERS PER LONGEST LIVED PARENT
- ESTIMATED RANDOM UNCERTAINTY REPORTED IS ONE STANDARD DEVIATION, IS.
SMALL NEGATIVE AND OTHER RESULTS LESS THAN OR EQUAL TO 25 ARE INTERPRETED BY RESL AS INCLUDING "ZERO" OR AS NOT DETECTED.
j FOR RESULTS GREATER THAN 25 BUT LESS THAN OR EQUAL TO 35, DETECTION IS QUESTIONABLE..RESULTS GREATER THAN 3S INDICATE DETECTION.
O IS THE ESTIMATED OVERALL UNCERTAINTY.
.-.,m.
" " ~ "
Table 4 a+
UNITED STATES DEPARTMENT OF ENERGY IDABO CPERATIONS OFFICE
~ ' -
RADIOLOGICAL AND ENVIRONMENTAL SCIENCES LABORATORY SAMPLE RECORD SHEET SERIAL NO.
14387CJ NRCS
- NRC MOD NO. ??????
- INPLANT DATE NEEDED 01/11/88 NONROUTINE SAMPLE DATE 12/14/87 SAMPLE SENT 12/21/87 ANALYZED.BY: J.S.MORTON, S.GIMPEL-SAMPLE HOUR 1200 MST SAMPLE RECEIVED 12/29/87 ORGANIZATION NRCS HARDCOPY PRINTOUT 01/20/88 ORIGINAL SIGNED BY: D.B. MARTIN COMMENTS:
NRC; COLLECTED BY D.D.
SKOV; GA TECHNOLOGIES; SOIL FROM DIRT PILE, SERVICE CORRIDOR TO RM 331; (URANIUM BY GAMMA SCAN)
COLLECTION DATE:
12/14/87 ANALYSIS DATE:
01/07/88 DECAY TIME 24.9 DAYS
- COUNT TIME 60 MIN.
DETECTOR NUMBER 6
SAMPLE SIZE 2.90E+02 g TOTAL GROSS BKGD MINOR NET ISOTOPE RESULTS +/- IS;O**
COUNT COUNT COUNT COUNT COUNT C/M C/M C/M C/M uCi/ gram l
0 0.00 0.00 Co 60
(
0 +/-
5; 5 )E -8
{
-9
-0.15
-0.15 CsD137
( -4 +/-
4; 4 )E -8 l
271 4.52 0.12 4.40 K 40
( 2.09 +/- 0.14;0.16 )E -5
~
-1
-0.02
-0.02 PaM234
(
0 +/-
6; 6 )E -6 j
57 0.95 0.24 0.23 0.48 U 235
(
6 +/-
5; 5 )E -8 i
i
- DECAY CORRECTION OF NATURAL CHAIN DAUGHTERS PER LONGEST LIVED PARENT 1
- ESTIMATED RANDOM UNCERTAINTY REPORTED IS ONE STANDARD DEVIATION, 15.
SMALL NEGATIVE AND OTHER i
RESULTS LESS THAN OR EQUAL TO 25 ARE INTERPRETED BY RESL AS INCLUDING "ZERO" OR AS NOT DETECTED.
FOR RESULTS GREATER THAN 2S BUT LESS THAN OR EQUAL TO 35, DETECTION IS QUESTIONABLE.
RESULTS GREATER THAN 3S INDICATE DETECTION.
O IS THE ESTIMATED OVERALL UNCERTAINTY.
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