ML20140G684

Insp Rept 70-1100/97-01 on 970414-17.No Violations Noted. Major Areas Inspected:Activities Associated W/Decontamination & Decommissioning of Former Nuclear Fuel Manufacturing Facility & Other Activities

ML20140G684
Person / Time
Site:	07001100
Issue date:	06/10/1997
From:	Bellamy R, Kottan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20140G665	List: ML20140G660 ML20140G684
References
70-1100-97-01, 70-1100-97-1, NUDOCS 9706170024
Download: ML20140G684 (15)

Text

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U.S. NUCLEAR REGULATORY COMMISSION .

REGION I f

Report No: 070-1100/97-01 License No: SNM-1067 Licensee: ABB Combustion Enoineerina incorocrated -

2000 Dav Hill Road l Windsor. Connecticut 06095-0500 i

l Facility: Nuclear Fuel Facilitv  !

! Inspection At: Windsor. Connecticut I i

Inspection Dates

Aoril 14-17.1997  :

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Inspector:  %- 6-/0 77 J. Kottanhealth Physics Manager Date Decommissioning and Laboratory Branch APPROVED BY: -

4 - /G 97 l Bellamy, Chief Date Decommissioning and Laboratory Branch Areas insoected: Announced inspection of the activities associated with the decontamination and decommissioning of the former nuclear fuel manufacturing facility and other activities j associated with license SNM-1067. Areas reviewed were those related to a confirmatory survey l of Building 21 which included: fixed contamination surveys, removable contamination surveys, and direct radiation measurements inside Building 21; fixed contamination surveys, removable contamination surveys, and direct radiation measurements on the paved areas outside of Building 21; and soil samples and direct radiation measurements around the perimeter of Building 21.

Insoection Summarv: No radioactive contamination or radiation levels above background were measured. No safety concerns or violations of regulatory requirements were observed.

i 0FFICIAl. RECORD COPY l Jg6q g g g g}joo HETURN ORIGINAL 10 -

! C PDR _ , REGION I

4 DETAILS i 1.0 INDIVIDUALS CONTACTED Principal Licensee Employees N. Azzam, Site Remediation Services J. Blute, Site Remediation Services J. Conant, Site Remediation Services  ;

J. Limbert, Site Remediation Services S. Masciulli, Radiological Services R. Scheeran, Site Remediation Services  ;

S. Sorensen, Field Services D. Waters, Site Remediation Services State of Connecticut Personnel G. McCahill, Department of Environmental Protection D. Wozniak, Department of Environmental Protection  ;

Denotes those present at the exit meeting on April 17,1997.

The inspector also interviewed other licensee personnel including members of the licensee's Site Remediation Services staff.

2.0 PURPOSE The purpose of this inspection was to perform a confirmatory survey of Building 21, which was used a warehouse and storage area to support fuel manufacturing in Building 17.

3.0 CONFIRMATORY SURVEY 3.1 Fixed Survev l A radiation survey for fixed contamination was performed on the floor and lower walls of the interior of Building 21. A radiation survey for fixed centamination was also performed on the exterior lower walls of the building as well as on the paved surfaces surrounding the building. The survey locations were chosen based on two criteria: first the locations which exhibited questionable negative values in the licensee's Final Status Survey Report, that is those locations with negative results l which were greater than twice the uncertainty of the result, and secondly 10% to 15% of licensee survey locations chosen on a random basis.

The fixed survey was performed with a Berthold/EG&G LB122 survey meter (NRC Tag No. 057021) utilizing a proportional detector filled with butane / propane counting gas. The efficiency of the detector was determined with NIST traceable alpha and beta standards. A check source was counted periodically during the survey in order to assess instrument performance and ensure proper operation. The

4 survey was performed with the LB122 operating on the beta plateau in order to detect both alpha and beta emissions from Uranium and its progeny. Several gross measurements were also made on the alpha plateau at selected locations.

The results of the fixed survey itedicated that no areas were found which were in excess of background. The data are presented in Table i and Table 11.

3.2 Wioe Survev Wipes were taken of the interior floor and lower walls and the exterior lower walls of Building 21 in order to measure any loose removable radioactive contamination.

Wipes were also taken of the paved surfaces surrounding Building 21. The wipes ,

were taken at the same locations at which the fixed surveys were made. Each wipe covered approximately 100 square centimeters.

The wipes were analyzed on a low background gas flow proportional counter I located in the NRC Region I office. The counter was calibrated with NIST traceable ,

alpha and beta standards. Gross alpha and gross beta analyses were performed on 1 the wipes.

The results of the wipe analyses indicated no positive sample results. (That is no positive alpha plus beta result.) The data are presented in Table I and Table ll.

3.3 Direct Radiation Measurements Direct radiation measurements were made at various locations both inside and outside of the building using a Ludlum Model 19 Micro R meter (NRC Tag No.

15521). Direct radiation measurements were also made at each soil sampling location. All readings were within the range of ambient background. The data are presented in Table I, Table 11 and Table Ill.

3.4 Soil Samoles Soil samples to a depth of 15 cm were taken at random locations within and beyond the fence surrounding Building 21 but no further than one meter beyond the fence. The licensee had defined the Building 21 area to be released as Building 21 plus the area around Building out to one meter beyond the fence. The licensee had marked this area, one meter beyond the fence, so that it can be identified even if the fence is removed.

The soil samples were analyzed for U-238 (Pa-234m progeny) and U-235 on a gamma spectrometry system located in the Region I office. The gamma spectrometry system is calibrated with NIST traceable standards.

The uranium concentration in the soil was within the range of naturally occurring uranium in soil. The data are presented in Table 111. See Attachment 1 for the location of the soil samples.

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3.5 Backaround Measurement Background measurements were made at various locations on and offsite. These locations were chosen because they duplicated the concrete and asphalt of Building 21 as reasonably as possible with respect to the type of materials used in construction and the age of the materials. The background data are presented in Table IV.

3.6 Other Tables The NRC release criteria and the detection limits for the various surveys and analyses are presented in Table V and Table VI.

4.0 EXIT MEETING The inspector met with the licensee representatives denoted in Section 1.0 of this report at the conclusion of the inspection on April 17,1997. The inspector summarized the purpose, scope and findings of the inspection. The inspector stated that the NRC confirmatory survey indicated that Building 21 met the NRC criteria for release from licensing restrictions and after NRC approval could be released for unrestricted use.

The licensee acknowledged the inspection findings.

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l i TABLE I BUILDING INTERIOR SURVEY RESULTS t

Location Description Alpha + Beta Direct Alpha Alpha Beta DPM/100 cm 2 Radiation DPM/100 cm 2 DPM/100 cm 2 DPM/100 cm 2 Fixed Survey pR/hr Fixed Survey Removable Removable  ;

(Net) (Gross) (Gross) (Net) (Net)

C-3 Floor 0130 7.0 NP -0.5 i O.8 613 i

J-9 Floor -70i30 7.5 NP -0.5 i O.8 312 '

K-16 Floor -60 i30 7.0 NP 1.411.2 813 U-16 Floor 10i30 7.0 NP O.5 i 1.0 2i2 H-1 Floor -10130 7,9 NP O.5 11.0 6 3 X-14 Floor -60 30 6.5 NP O.O i O.9 1 2 0-1 Floor -40130 7.0 NP O.5 i 1.0 3i3  ;

W-1 Floor 30 30 7.5 NP -0.510.8 212 W-3 Floor 40 30 6.5 NP O.911.1 012 Q-5 Floor -20 i30 7.1 NP -0.510.8 2i2 W-7 Floor -40130 6.9 NP O.O O.9 112 S-7 Floor -80130 7.0 NP O.010.9 1 2 0-9 Floor -60130 7.1 NP -0.5 i O.8 Si3 S-11 Floor -40 i30 6.8 NP 1.4 i 1.2 3i2 M-20 Floor -40 i30 7.2 NP O.511.2 1113 F-26 Floor -40130 7.0 NP -0.510.8 112  ;

I TABLEI BUILDING INTERIOR SURVEY RESULTS Location Description Alpha + Beta Direct Alpha Alpha Beta DPM/100 cm 2 Radiation DPM/100 cm DPM/100 cm 2 DPM/100 cm 2 Fixed Survey pR/hr Fixed Survey Removable Removable (Net) (Gross) (Gross) (Net) (Net)

S-24 Floor 10130 7.0 NP O.911.1 112 C-32 Floor -10 30 7.4 NP O.O i O.9 413 .

1-35 Floor -10130 7.0 NP 1.4 1.2 2i2 ,-

W-35 Floor -3O i 30 6.8 IIP O.0 10.9 li2 SQA Wall -100i 20 NP WP O.0 1 0.9 -212  :

(wood)

SFAA Wall 524 i16 NP NP -0.5 i O.8 112 (insulation) (gross)

W26A Wall -80 + 90 NP NP O.9 11.1 Oi2 i (wood) i NQA Wall -55 i 20 NP NP O.0 1 0.9 012 Nood) -

Ell A W all 515115 NP NP O.0 10.9 -l i 2 ,

(insulation) (gross)

NMAA W all 515i15 NP NP O.5i1.0 -1 2 (insulation) (gross) 1-5 Floor 0130 NP 1113 NP NP -

(gross)  :

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i TABLEI BUILDING INTERIOR SURVEY RESULTS Location Description Alpha + Beta Direct Alpha Alpha Beta DPM/100 cm2 Radiation DPM/100 cm 2 DPM/100 cm 2 DPM/100 cm 2 t

h Fixed Survey pR/hr Fixed Survey Removable Removable  ;

(Net) (Gross) (Gross) (Net) (Net)

P-5 Floor -30i30 NP 913 NP NP (gross) ,

H-15 Floor -60130 NP Si3 NP NP  ;

(gross)

L-25 Floor -40 i30 NP Si2 NP NP (gross)

R-25 Floor 10 30 NP 512 NP NP (gross)

NOTES: NP= not performed at that location. Note that some measurements are gross measurements. Reported uncertainties t are 1 sigma (1s) counting uncertainty. Direct radiation measurements were made at a height of 1 meter above the floor.

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TABLE ll BUILDING EXTERIOR SURVEY RESULTS Location Description Fixed Survey Gross Direct Net alpha Net beta DPM/100 cm2 Radiation DPM/100 cm 2 DPM/100 cm 2 (Net) pR/hr removable removable I 1 Pavement 50130 8.5 0.O i O.9 012  :

(concrete) j 6 Pavement 70130 7.5 0.O i O.9 -312 (asphalt)  ;

9 Pavement 120 30 7.5 0.9 i l .1 1 2 (asphalt) 13 Pavement 30130 7.8 -0.5 i O.8 312 (asphalt) i 17 Pavement 9i30 6.9 0.O i O.9 li2 (asphalt) 19 Pavement -20130 6.6 -0.5 i O.8 -1 i 2  :

(asphalt)  :

21 Pavement 110 130 7.1 1.8 i l .3 312 (concrete) 23 Pavement 40i 30 7.0 -0.9 i O.6 3i2 ,

(asphalt) 24 Pavement 40130 7.1 0.S i 1.0 1t2 (asphalt) l 27 Pavement 30i30 7.5 0.0 1 0.9 Oi2 (asphalt) i f

TABLE ll BUILDING EXTERIOR SURVEY RESULTS location Description Fixed Survey Gross Direct Net alpha Net beta DPM/100 cm 2 Radiation DPMI100 cm2 DPM/100 cm 2 (Net) pR/hr removable removable 30 Pavement 60 i30 7.0 -0.510.8 312 (concrete) '

1 South wall -30 i 20 NP O.S i 1.0 5i3 6 South wall Oi 20 NP -0.9 i O.6 -112 13 South wall -30 20 NP O.5 11.0 012 19 East wall -40120 NP -0.910.6 1*2 23 East wall 9 20 NP 1.4 i l .2 112 Center North wall 30120 NP 1.8 11.3 2i2 Center West wall Oi20 NP 1.4 i1.2 012 -

i NOTES: NP=not performed at that location. Note that some measurements are gross measurements. Reported uncertainties  ;

are i 1 sigma (1s) counting uncertainty. Direct radiation measurements were made 1 meter above the ground. i M

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i TABLE Ill l

SOIL SAMPLE RESULTS l Sample Number U 235 (pCi/g) U-238 (pCi/g) pR/hr @ 1 meter 1

1 0.06 0.02 0.5 i O.5 9.1 l l

2 0.09i0.03 < 0.9 10.0 l

! 3 0.08 0.03 <2 10.1 4 0.16 0.02 0.9

• 0.6 10.0 5 0.10 i O.03 1.4 i O.8 10.1 6 0.10 i O.02 2.3 i 0.8 10.7 7 0.05 i O.02 1.5 i O.6 11.2 ,

l 8 0.06 i O.02 0.6 0.6 10.4 9 0.04*0.02 1.3 iO.9 9.9 ,

Background 0.05 0.03 < 0.9 10.2 l (opposite Bldg.

8A)

Background 0.06*0.03 1.5 i O.8 11.1 i (opposite fossile l unit)

NOTE: uranium concentrations were determined on a dry weight basis. Reported uncertainties are i 1 sigma (1s) counting uncertainty. Refer to Attachment 1 for sampling locations.

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. TABLE IV BACKGROUND MEASUREMENTS Direct Radiation Measurements (at one meter) 1.10.2 R/hr near Building 8A (soil sample no.10).

2.11.1 pR/hr in woods opposite fossile unit ( soil sample no.11).

3.10.5 pR/hr on asphalt opposite gate to Building 21,

4. 8.1 R/hr on asphalt at sewage treatment plant.

5. 7.5 pR/hr on asphalt at Building 4 parking lot opposite Building 7.

6. 8.2 pR/hr on concrete sidewalk near cafeteria building.

7. 8.8 pR/hr on concrete side walk opposite Building 19.

8. 9.5 R/hr at State boat launch area on Farmington River.

Ei_xed Survev Measurements

1. 880i20 dpm on asphalt opposite gate to Building 21.

2. 840120 dpm on asphalt at sewage treatment plant, ,

3. 890i20 dpm on asphalt at Building 4 parking lot opposite Building 7.

4. 860 20 dpm on concrete sidewalk near cafeteria building.

5. 960 20 dpm on concrete sidewalk opposite Building 19.

6. Concrete floor areas in Building 20:

791 dpm,782 dpm,819 dpm,810 dpm Average = 800 i 20 dpm.

7. Concrete floor areas in Building 7:

856 dpm,764 dpm,791 dpm,819 dpm Average = 810 i40 dpm.

8. Average of dpm values from 6 and 7 above: 800 i 30 dpm.

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. TABLE V RELEASE CRITERIA Removable Surface contamination: 1000 dpm/100 cm2 (above background).

Average Fixed Surface Contamination: 5000 dpm/100 cm2(above background).

Maximum Fixed Surface Contamination: 15000 dpm/100 cm2 (above background).

Exposure Rate at 1 meter above a surface: <or = SuR/hr (above background).

Soil Contamination (Uranium): <or = 30pCi/g (above background).

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TABLE V1

i. DETECTION LIMITS i l SURVEY TYPE MDA

! Fixed (concrete) 130 dpm/100 cm2 L

Fixed (asphalt) 130 dpm/100 cm 2 Fixed (wood) 80 dpm/100 cm 2 Removable-alpha 4 dpm/100 cm 2 l

Removable-beta 8 dpm/100 cm 2 l Direct Radiation approximately 2 uR/hr l

Soil Varies by soil type and l interferences present-see l Table Ill.

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ATTACHMENT 1 SOIL SAMPLING LOCATIONS

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l ATTACHMENT 1 SOIL SAMPLING LOCATIONS

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