ML20217B779
| ML20217B779 | |
| Person / Time | |
|---|---|
| Issue date: | 03/20/1998 |
| From: | Jorgensen B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20217B763 | List: |
| References | |
| REF-QA-99990063-980320 99990063-97-07, 99990063-97-7, NUDOCS 9803260174 | |
| Download: ML20217B779 (11) | |
Text
4 U.S. NUCLEAR REGULATORY COMMISSION REGIONlli License No: Non-Licensee Docket No: 999-90063 Report No: 999-90063/97007(DNMS)
Organization: Englehard Corporation Facility: Englehard Corporation Buildings Location: 1000 Harvard Avenue Cleveland, Ohio Dates: October 20-21,1997 December 18-19,1997 March 4 and 17,1998 inspectors: D. W. Nelson, Radiation Specialist P. J. Lee, Radiation Specialist Accompanying Personnel: Celeste Lipp, Ohio Department of Health, Bureau of Radiation Protection Mike Snee, Ohio Department of Health, Bureau of Radiation Protection Chuck McCracken, Ohio Department of Health, Bureau of Radiation Protection Approved By: Bruce L. Jorgensen, Chie Decommissioning Branch Division of Nuclear Materials Safety l
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EXECUTIVE
SUMMARY
Englehard Corporation NRC Inspection Report 999-90063/97007(DNMS)
Confirmatory surveys of the interior surfaces of Englehard Buildings W-1 (Warehouse); L-1; E-1 (Garage); R-3 (Northside Locker Room); L-2 (Southside Locker Room); L-5 (Raw Shed); H-11 and related Electrical Building; and Building F-1 (Foundry) were conducted to determine if the licensee's final survey data accurately reflected the condition of the buildings, and to independently survey for residual contamination. The confirmatory surveys did not identify any residual surface contamination within the Englehard Buildings surveyed in excess of the NRC's unrestricted release guidelines.
Soil samples were collected under the floor of Building F-1 (Foundry), where cracked concrete and soil had been removed. Arialysis of the samples in the NRC Region ill laboratory showed the average concentration was less than NRC unrestricted release guidelines.
Wipe samples were collected at various locations in Buildings W-1 (Warehouse) and F-1 (Foundry) and were analyzed in the Region tillaboratory. None of the wipe samples contained detectable activity.
Buildings W-1 (Warehouse); L-1; E-1 (Garage); R-3 (Northside Locker Room); L-2 (Southside Locker Room); L-5 (Raw Shed); H-11 and related Electrical Building; and Building F-1 (Foundry) meet NRC criteria for release for unrestricted use.
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Report Details 1.0 Background Natural uranium was used in the production of uranium hexafluoride for the Manhattan Engineering District and Atomic Energy Commission (AEC) in the 1940's and 1950's at this site. Building G (see Attachment B) was the main processing building. Building G is 2
a three story building made of brick and concrete and has approximately 66,500 ft of floor surface. Building G was decommissioned by the Harshaw Chemical Company and released from AEC control in 1960. Currently, the Englehard Corporation owns all of the buildings on the site except for Building G, which is owned by the Chevron Chemical Company.
- From 1976 through 1979, surveys of the site were conducted by Argonne National Laboratory for the Department of Energy (DOE). These surveys identified residual uranium contamination in excess of NRC release limits within Building G. The other buildings were also surveyed and several were found to be contaminated in excess of release guidelines.
In early 1997, an Englehard contractor, B. Koh & Associates, Inc., began remediating all of the contaminated buildings owned by Englehard. Chevron has indicated that Building G will be remediated at some future date.
2.0 Confirmatory Surveys 2.1 Inspection Scope (87104)
The NRC confirmatory surveys wete conducted in accordance with Inspection Procedure 87104. The surveys included direct surface scanning surveys of interior surfaces (floors, lower walls, interior ceilings and upper walls) within designated affected buildings ard minimal random direct surface scanning surveys within designated unaffected buildings. The surveys also included measuring exposure rates one meter above the floors and the collection of smears from the floors and lower walls.
Direct surface scanning surveys of the building floors were conducted using gas flow proportional floor monitors and/or Geiger-Mueller (G-M) pancake probes. Direct surface scanning of interior walls and ceiling rafters were performed using GM pancake probes.
Exposure rates were measured at a height of one meter above the building floors using Ludium Model 19 micro R meters. See Attachment A for details on survey instruments.
Efficiencies were calculated for the direct surface survey instruments prior to arriving at the site, Due to surface attenuation, most of the particles detected were expected to be high energy beta; only a very small percentage of alpha was expected to be detected.
Therefore, based on the ratio of alpha to beta activity, beta measurements were used to determine the alpha surface activities of source materials.
The NRC's unrestricted release guidelines for depleted uranium (DU) for fixed activity on building surfaces are 5000 disintegrations per minute (dpm) (84 becquerels (Bq))/100 -
square centimeters (cm2) beta activity averaged over an area not to exceed one square meter, and 15,000 dpm (250 Bq)/100 cm2 maximum beta activity over an area not to 2
exceed 100 cm'E The guidance is 1000 dpm (17 Bq)/100 cm for removable beta activity.
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These guidelines are found in the NRC's " Guideline for Decontamination of Facilities and Equipment prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material," dated August 1987.
2.2 Observations and Findinas 2.2.1 Buildings H-11 and Related Electrical Building and R-3 (North Locker Room)
Englehard Corporation classified the interiors of Buildings H-11, the Related Electrical Building and R-3 (North Locker Room) unaffected areas based on record searches and interviews with personnel familiar with activities conducted in the buildings. Englehard Corporation's final survey reports dated January 2,1998, and January 6,1998, for the buildings were reviewed by the NRC prior to visiting the site. The final survey data indicated that the areas surveyed were less than the NRC unrestricted use guidelines.
Based on reviews of the final survey report and previous NRC experience with confirmatory surveys performed by Englehard Corporation's contractor (B. Koh &
Associates), confirmatory surveys were deemed unnecessary and were not performed within these buildings. l 2.2.2 Building L-2 (Southside Locker Roorn) i Englehard Corporation classified the interior of Building L-2 an unaffected area based on searches of the records. Englehard Corporation's final survey report for the building dated December 16,1997, was reviewed by the NRC prior to conducting the confirmatory survey. The final survey data indicated that the areas surveyed were less than the NRC unrestricted use guidelines.
The inspectors performed direct surface scanning surveys on approximately 20% of the building's floor and 100% of the building's shower floor drains using a GM pancake probe.
No residual activity above background was detected on the floors or in the shower drains.
2.2.3 Building L-5 (Raw Shed)
Englehard Corporation classified Building L-5 an unaffected area based on searches of the records. Englehard Corporation's final survey report for the building dated August 12, 1997, was reviewed by the NRC prior to conducting the confirmatory survey. The final survey data indicated that the areas surveyed were less than the NRC unrestricted use guidelines The inspectors performed direct surface scanning surveys on approximately 50% of the building's floor and interior lower wall surfaces using a GM pancake probe. No residual activity above background was detected on the floors or lower wall surfaces.
2.2.4 Building L-1 Englehard Corporation classified Building L-1 an unaffected area based on searches of I' the records. Englehard Corporation's final survey report for the building dated August 12, 1997, was reviewed by the NRC prior to conducting the confirmatory survey. The final l
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survey data indicated that the areas surveyed were less than the NRC unrestricted use guidelines.
The inspectors performed direct surface scanning surveys on approximately 20% of the building's floor,60% of the lower wall surfaces and 100% of the open floor drains using a G-M pancake probe. No residual activity above background was detected on the floors, the lower wall surfaces or the open floor drains.
2.2.5 Garage Englehard Corporation classified the interior surfaces of the garage as unaffected areas based on searches of the records. Englehard Corporation's final survey report for the garage dated August 12,1997, was reviewed by the NRC prior to conducting the confirmatory survey. The final survey data indicated that the areas surveyed were less than the NRC unrestricted use guidelines.
The inspectors performed direct surface scanning surveys on approximately 20% of the building's floor using a gas flow proportional floor monitor and 30% of the lower wall surfaces using a G-M pancake probe. No residual activity above background was detected on the floors or lower wall surfaces.
2.2.6 Warehouse (Building W-1)
Englehard Corporation initially classified the interior surfaces of the garage as unaffected areas based on searches of the records. However, the characterization surveys found discrete areas of elevated activity on the warehouse floors. Those and surrounding areas were subsequently reclassified affected areas. Englehard Corporation's final survey report for the warehouse dated August 12,1997, was reviewed by the NRC prior to conducting the confirmatory survey. The final survey data indicated that the areas surveyed were less than the NRC unrestricted use guidelines.
The inspectors performed direct surface scanning surveys on approximately 50% of the building's floor using a gas flow proportional floor monitor and 30% of the lower wall surfaces using a G-M pancake probe. A limited number of dose rates were measured at one meter above the floor. Smears collected on floors and lower walls were taken to the NRC Region ill analytic laboratory for analysis.
The inspectors found several isolated areas on the warehouse floor where contamination levels exceeded the NRC release guidelines. Those areas were subsequently remediated by the contractor and resurveyed. No additional residual activity above the NRC unrestricted use guidelines was detected on the floors or lower wall surfaces. The smear samples were analyzed using the NRC Region til gas flow proportional counter (Gamma Products G-5000) and gross alpha / beta activity on the smears was less than the counter's MDA. Exposure rate measurements, which ranged from 7 to 15 microroentgens per hour (uR/h) (1.8 to 3.7 nanocoulombs per kilogram per hour (nC/kg/h)), were indistinguishable from background.
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2.2.7. Foundry (Building F-1)
Englehard Corporation classified the interior surfaces of the foundry as affected areas -
based on searches of the records. The inspectors performed confirmatory surveys in the Foundry on three separate occasions; October 20-21,1997, and December 18-19,1997, and March 4,1998. The first survey, October 20-21,1908, was performed before the Englehard Corporation's final survey report for the Foundry had been issued. Englehard Corporation's final survey report for the Foundry dated December 15,1997, was reviewed by the NRC prior to conducting the confirmatory surveys on December 18-19,1998 and March 4,1998. The final survey data indicated that the areas surveyed were less than the NRC unrestricted use guidelines.
During the October 20-21,1997, confirmatory survey, the inspectors performed direct surface scanning surveys on approximately 20% of the Foundry's floor using a gas flow proportior,al floor monitor and 20% of the lower wall surfaces using a G-M pancake probe. The inspectors found contamination in excess of the NRC unrestricted use guidelines on the Foundry floor, in cracks in the Foundry floor and on the lower foundry walls. The results of the surveys were discussed during an on-site meeting on October 21,1997, and the Englehard Corporation representative indicated that further remediation would be preformed in the Foundry prior to issuing the final survey report.
During the December 18-19,1997, confirmatory surveys, the inspectors performed direct surface scanning surveys on approximately 50% of the Foundry's floor using a gas flow proportional floor monitor and 50% of the lower wall surfaces using a GM par. cake probe.
Contamination levels on the floors and walls were less than the NRC unrestricted use guidelines. The inspectors did, however. find low levels of contamination in loose dust on the Foundry floor (sample # 6, Attachment C) and in dust on the ceiling rafters. At the exit meeting on December 19,1997, the Englehard representative agreed to vacuum the Foundry floor and ceiling rafters to remove any loose dust that had accumulated..
During the December 18-19,1997, confirmatory surveys smear samples were also collected on the floors and lower walls. The smears were retumed to the Region lli analytic laboratory for analysis using the NRC Region ill gas flow proportional counter (Gamma Products G-5000). Gross alpha / beta activity on the smears was less than the counter's MDA. Random exposure rate measurements at one meter above the floor ranged from 7 to 15 microroentgens per hour (uR/h) (1.8 to 3.9 nanocoulombs per kilogram per hour (nC/kg/h)) and were essentially indistinguishable from background.
During characterization of the Foundry, Englehard Corporation found contamination in large cracks on the Foundry floor. To remove the contamination in the cracks several large sections of the floor were removed down to the underlying ground. Following excavation, Englehard surveyed the exposed concrete and ground and collected soil samples from the exposed ground. Englehard Corporation's finai survey report for the Foundry dated December 15,1997, indicated that the contamination levels on the exposed concrete and ground had been remediated to levels that were less than the NRC unrestricted use guidelines. ,
The inspectors performed direct surface scanning surveys on the exposed concrete and ground and collected soil samples from the exposed ground. The soil samples were sent to the Region 111 analytic labomtory for analysis. The direct surveys found no residual 6
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activity above the NRC unrestricted use guidelines on the exposed concrete or ground.
Only one of the five soil samples had residual uranium above NRC criteria for free release (Attachment C), and the average activity for all five samples was less than NRC unrestricted use guidelines.
During the December 18-19,1997, site visit the Englehard representative indicated that remediation of several rooms located in the northeast comer of the Foundry had not been completed. On February 20,1998, Englehard issued the Final Radiological Survey Report for those rooms. The report indicated that the contamination levels in the rooms had been reduced to levels that were less than the NRC unrestricted use guidelines.
On March 4,1998, the inspectors performed confirmatory surveys in the rooms located in the northeast comer of the Foundry. The inspectors performed direct surface scanning surveys on approximately 50% of the room's floors and lower walls. No residual activity above the NRC ursrestricted use guidelines was detected on either the floors or the lower walls. Smear samples collected on the room's floors and lower walls and were analyzed using the NRC Region ill gas flow proportional counter (Gamma Products G-5000). The gross alpha / beta activity on the smears was less than the counter's MDA. Random l exposure rates were measured at one meter above the floors. The exposure rates l ranged from 7 to 15 microroentgens per hour (uR/h) (1.8 to 3.7 nanocoulombs per kilogram per hour (nC/kg/h)) and were indistinguishable from background.
During the March 4,1998, confirmatory survey site visit the inspectors noted that dust on the Foundry floor and ceiling rafters had been removed and placed in containers for eventual disposal. Direct surveys on the floors and ceiling rafters indicated that the removal of the dust had reduced the residual activity levels on the effected floors and ceiling rafters to levels that were barely distinguishable from background.
2.3 Conclusions The interior surfaces of Englehard Buildings W-1 (Warehouse); L-1; E-1 (Garage); R-3 (Northside Locker Room); L-2 (Southside Locker Room); L-5 (Raw Shed); H-11 and related Electrical Building; and Building F-1 (Foundry) were surveyed for residual contamination. The confirmatory surveys did not identify any residual surface contamination within the Englehard Buildings that had been surveyed in excess of the NRC's unrestricted release guidelines. Based on these results, Englehard Buildings W-1 (Warehouse); L-1; E-1 (Garage); R-3 (Northside Locker Room); L-2 (Southside Locker Room); L-5 (Raw Shed); H-11 and related Electrical Building; and Building F-1 (Foundry) can be released for unrestricted release.
3.0 Exit Meeting i
At the conclusion of the onsite inspection on March 4,1998, the preliminary results of the j confirmatory surveys were discussed with the individuals identified below. Subsequently, on March 17,1998, on completion of analyses of wipe samples by the NRC Region Ill laboratory, the results of those analyses were discussed with Mr. Kopas.
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PERSONS CONTACTED
- A. Kopas, Englehard Corporation T. Adams, B. Koh & Associates
- Indicates those present at the exit meeting on March 4,1997.
INSPECTION PROCEDURE USED 87104 Decommissioning inspection Procedure for Materials Licensees LIST OF ACRONYMS USED DU depleted uranium G-M Geiger-Mueller uR/h microroentgens per hour MDA minimum detectable activity nC/kg/h nanocoulombs per kilogram per hour ATTACHMENTS Attachment A: Survey Instruments Attachment B: Site Map i Attachment C: Foundry Exposed Ground and Dust Sample Results ]
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Attachment A Survev Instruments instrument Model No. Serial No. Detector Last Calibration Ludlum 2241-2 130052 Ludlum 44-9 07/14/97 Ludlum 2221 115135 Ludlum 239-1F 08/18/97 (Ohio) 2221 127229 Ludlum 239-1F 05/23/97 Ludlum (Ohio) 2221 127238 Ludlum 239-1F 05/17/97 Ludlum Ludlum 19 21567 N/A 04/11/97 The beta efficiency for the Ludlum 2241-2 meter with the Ludlum 44-9 probe was about 25 percent. The beta efficiency for the Ludlum 2221 meter with the Ludlum 239-1F detector was about 35 percent. A Cs-137 foil source was used for the calibration. The background for the GM pancake probes (Ludlum 44-9) varied from 30 to 80 counts per minute (cpm), depending on the surface materials, such as concrete block, glazed brick, glass, metal, wood, etc. The background for the gas flow proportional detector (Ludlum 239-1F) varied from about 900 ;
to 1300 cpm, depending on the composition of the floor. The Model 19 meters varied from 7 to i 15 microroentgens per hour background radiation (pR/h) (1.8 to 3.9 nanocoulombs per kilogram j per hour (nC/kg/h)), depending on the composition of the surrounding structures, l
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. 1 Attachment C l Engelhard Corporation Sampling Results of Foundry Building (pCi/ gram) sample no. Uranium (234+235+238) Sample Description 1 20.9 i 5.0 soil under the contaminated concrete floor (1) 2 18.8 i 4.6 soit under thecontaminated concrete floor (1) 3 80.1 i 8.6 soit under the contaminated concrete floor (2) l 4 4.6 i 1.4 soil under the contaminated concrete floor (2) 5 10.71 3.2 soil under the contaminated concrete floor (2) 6 406.3 1 29.6 loosed dust / dirt collected from the floor i l
- The soil samples contain processed natural uranium; the released criteria is 30 pCi/ gram.
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