ML20248C113

Insp Rept 70-0133/98-03 on 980514-26.No Violations Noted. Major Areas Inspected:Special Announced Insp to Perform Confirmator Radiological Survey of Low Level Radioactive Waste Drum Storage Area of Former Clevite Facility

ML20248C113
Person / Time
Site:	07000133
Issue date:	05/28/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20248C095	List: ML20248C090 ML20248C113
References
70-0133-98-03, 70-133-98-3, NUDOCS 9806020067
Download: ML20248C113 (14)

Text

U.S. NUCLEAR REGULATORY COMMISSION R E GIO N lil Docket No: 070-00133 (Terminated)

License Nos: SNM-183 (Terminated)

C-3692; C-3790 (Terminated) 34-00653-01/02 (Terminated)

Report No: 070-00133/98003(DNMS)

Licensee: Clevite Corporation Facility: Shorebank Enterprise Group Location: 540 East 105th Street Cleveland, OH 44108 Dates: May 14,1998 May 26,1998 Inspectors: John E. House, Senior Radiation Specialist John T. Buckley, Project Manager Accompanying James Webb Personnel: Ohio Department of Health Approved By: Bruce L. Jorgensen, Chief Decommissioning Branch Division of Nuclear Materials Safety

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9906020067 990529 PDR ADOCK 07000133 C PDR

l EXECUTIVE

SUMMARY

l-FORMER CLEVITE FACILITY Inspection Report 070-00133/98003(DNMS) l l This was a special announced inspection to perform a confirmatory radiological survey of the low level radioactive waste drum storage area of the former Clevite facility. The purpose of this survey was to determine if the condition of the facility was accurately

described by the remediation contractor's final survey data and met the NRC unrestricted use guidelines.

! The confirmatory survey was based on NUREG/CR-5849. Scan surveys were performed on the floor, walls, and overhead areas. Dose rate measurements were made at one meter heights above the floor and ten wipe samples were taken along with one minute count measurements at each wipe location.

I Confirmatory survey and sample analytical results of the storage area did not identify any residual radioactive materialin excess of the NRC's unrestricted use guidelines for enriched uranium or thorium. The waste drum storage area meets the NRC criteria for unrestricted use.

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l l Report Details

1.0 Background i Special Nuclear Material License No. SNM-183 was issued to Clevite Research Center, Division of Clevite Corporation on March 10,1958. This license authorized the use and possession of enriched uranium (EU) at its facility located at 540 Fast ,

105th Street in Cleveland, Ohio. The licensed activities included melting, alloying, l forging, rolling, welding, pickling, machining, stamping, sintering, and chemical and i metallographic analyses of EU powder and ceramic materials for the production and fabrication of fuel elements for nuclear reactors. The license initially authorized about 9 kilograms (kgs) of 90% EU, and subsequent amendments raised this authorization to nearly 56 kgs. An area on the first floor in the rear of the building was reserved for fuel fabrication.

Other research activities, covered under Source Material License Nos. C-3790 and C-3692, authorized about 90 kgs of natural uranium and 5 grams of thorium l sulfide, respectively.

Gould, Inc., the successor of Clevite Corporation, contracted with Sevenson Environmental Services, Inc., (Sevenson) to develop and implement a remediation/ survey plan to render the property fit for release for unrestricted use.

The contractor submitted the Site Characterization Survey / Termination Survey,

Remediation, and Health and Safety Plan on May 10,1995, and was authorized by the NRC to proceed with site characterization in a letter dated June 1,1995.

The site characterization, remediation and final surveys have been completed.

Sevenson submitted the Final Status Survey Plan (FSP) to the NRC on November 24,1997. The FSP was approved by NRC on December 12,1997.

Previous inspections have verified that the responsible party has conducted remediation activities in accordance with its approved Remediation Plan. The facility, with the exception of the low level radioactive waste drum storage area, met the NRC release criteria defined in Guidelines for Decontamination of Facilities and Eauipment Prior to Release for Unrestricted Use or Termination of i Licenses for Bvoroduct. Source. or Special Nuclear Material, dated August,1987. I See inspection Reports 070-00133/95001,070-00133/95002,070-00133/96001, 070-00133/98001 and 070-00133/98002. l On May 14,1998, NRC personnel accompanied by a representative from the Ohio  ;

Department of Health, Bureau of Radiation Protection, conducted an inspection at the former Clevite Corporation facility site. The scope of the inspection was to '

i conduct a confirmatory survey of the low level radioactive waste drum storage area to determine if this area would meet the NRC release criteria defined above.

The surface contamination limits for Uranium are 5,000 disintegrations per minute (dpm) per 100 square centimeters with a maximum of 15,000 dpm and 1,000 dpm removable. For Thorium the limits are 1,000 dpm per 100 square centimeters with a ,

maximum of 3000 dpm and 200 dpm per 100 square centimeters removable. l 1

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2.0 - ' Inspection Activities 2.1 ~ Instrumentation. Survey Methods and Tables This confirmatory survey consisted of performing independent scan surveys, collecting wipe samples to determine the presenco of fixed and removable contamination, performing one minute count measurements of the areas where wipe samples were to be taken, and measuring exposure rates.

Scan surveys and one minute counts were conducted with Ludlum 44-9 Geiger-Mueller " pancake" probes connected to a Ludlum Model 3 rate meter or a Model 2249-2 rate meter / scaler. Scan surveys were conducted with the probe approximately one-half inch or less from the surface and at a scan speed of approximately one detector width per second. Area dose rate measurements were performed with Ludlum Model 19 micro R meters at a distance of one meter from the horizontal surface. Ten wipe samples were taken using laboratory grade 47 millimeter filter paper circles. Each sample area covered an area of approximately 100 square centimeters. Table 1 contains data for wipe samples including location and activity in disintegrations per minute and Table 2 contains survey instrument information.

2.2 Confirmatory Survey of the Waste Storaae Area of the Clevite Facility

a. Inspection Scope This confirmatory survey was conducted to determine the adequacy of the remediation contractor's final status survey and was based on NUREG/CR-5849, which recommends evaluation of approximately ten percent of the site. The inspectors evaluated approximately 90% of the floor area,30-90% of the wall area, and selected overhead areas that represented the oldest overhead structures. Both random and biased survey techniques were used.

Radiological surveys were performed in the following areas of the West Wing; Weld Shop outer area, Hall A, and Rooms 1,2 and 15. These rooms and areas formed one contiguous area since the interior dividing walls had been removed. This was  !

the area in which low level radioactive waste drums and contaminated equipment had been stored.

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b. Observations and Findinas inspectors performed scans of tha floors, walls and upper areas of the drum storage j area. The surveys emphasized crevices, wall /floorjunctions, drain areas, overhead l horizontal surfaces, and remediated areas. One minute count measurements and wipe samples were collected from floors and walls to determine if removable contamination was present above NRC release guidelines. Exposure rate readings were taken one meter above the floor in those areas surveyed during the inspection.

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i b.1 Weld Shop (outer area)

The inspectors performed an approximate 90% scan survey on the floor and walls. i Readings ranged from 43 - 80 counts per minute (cpm). These readings were consistent with backgre and measurements. Two wipe samples and one minute count measurements v,ere taken in this room (see attached grid map for sample locations). The one mimte count measurements, where smears were taken, ranged from 40 - 60 cpm. Resuas of the wipe samples are presented in Table 1. Activity on  !

the wipe samples was consistent with background, as were the one minute count i readings. Exposure rate measurements in this room ranged from 6 - 7 uR/hr which I was consistent with background.

b.2 Rooms 1 and 2 l

The inspectors performed an approximate 90% scan survey on the floor and the East l wall. Readings ranged from 40 - 80 cpm on the floor and from 20 - 100 cpm on the l wall. The variability in wall readings in this entire (contiguous) area was due to the )

varied wall composition which included brick, cinder block and dry wall. Three wipe samples and one minute count measurements were taken in this room (see attached grid map for sample locations). The one minute count measurements ranged from i 50 - 60 cpm. Results of the wipe samples are presented in Table 1. Activity on the wipe samples was consistent with background, as were the one minute count readings. Exposure rate measurements in this room ranged from 5 - 9 uR/hr. These readings were consistent with background.

b.3 Room 15

- The inspectors performed an approximate 90% scan survey on the floor and )'

approximately 30% scan survey on the walls to a height of 2 meters. Readings ranged from 40 - 80 cpm on the floor and 20 - 80 cpm on the wall (depending on  ;

material type). These readings were consistent with background measurements. '

Three wipe samples and one minute count measurements were taken in this room (see attached grid map for sample locations). The one minute count measurements ranged from 35 - 42 cpm. Results of the wipe samples are presented in Table 1.

Activity on the wipe samples was consistent with background, as were the one minute count readings. Exposure rate measurements in this room ranged from 4 - 7 uR/hr. These readings were consistent with background.

b.4 Hall A The inspectors performed an approximate 90% scan survey on the floor. Readings l ranged from 40 - 80 cpm with one small spot reading 150 cpm. These readings were consistent with background measurements except for the small spot of elevated activity (see attached grid map for location of area of elevated activity).

Six one minute count measurements were made (including the 150 cpm spot) within a square meter of this spot. The average reading over one square meter was 67 cpm, which was consistent with background. Two wipe samples and one n'inute count measurements were taken in this hall area (see attached grid map for sa'mple 5

't locations). The one minute count measurements ranged from 60 - 150 cpm.

Results of the wipe samples are presented in Table 1. One minute exposure rate i measurements in this room ranged from 6 - 7 uR/hr. These measurements were consistent with background.

c. Conclusions Data from scan surveys, one minute count measurements and wipe samples indicated that radioactivity was well within the NRC release guidelines. With the exception of the single elevated reading in Hall A, all measurements were consistent with background activity for the construction materials used in this building. When the single elevated spot was averaged over one square meter, the result was consistent with background activity. Analysis of the wipes showed that no residual loose radioactive material was present, and activity levels on the wipe samples were consistent with background levels and thus were well below NRC release guidelines for unrestricted release. The waste drum storage area meets the NRC criteria for unrestricted release.

3.0 Exit Meeting Summary At the conclusion of the inspection on May 14,1998, the preliminary results of the inspection were discussed with the individualidentified in this report. On May 26,1998, results of the sample analyses were discussed with the remediation contractor. None of the information I provided during the inspection was indicated to be proprietary.

Attachments: As stated i

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l PARTIAL LIST OF PERSONS CONTACTED i l Mr. Rory Grube, Radiation Safety Officer, Sevenson Environmental Serv c l

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TABLE 1 l WIPE DATA )

DISINTEGRATIONS PER MINUTE (DPM) PER 100 SQUARE CENTIMETERS SAMPLE WING ROOM GRID SURFACE ACTIVITY l DPM 98-30-001 WEST 15 M-16 CONCRETE <MDA )

98-30-002 WEST 15 K-11 CONCRETE <MDA 98-30-003 WEST 15 P-5 CONCRETE <MDA 98-30-004 WEST 2 G-10 CONCRETE <MDA 98-30-005 WEST 2 M-5 CONCRETE <MDA 98-30-006 WEST 2 M-10 CONCRETE <MDA 98-30-007 WEST WELD SHOP M-7 CONCRETE <MDA 98-30-008 WEST HALL A Q-5 CONCRETE <MDA 98-30-009 WEST WELD SHOP H-6 CONCRETE <MDA 98-30-010 WES'T HALL A J-4 CONCRETE <MDA MINIMUM DETECTABLE ACTIVITY (MDA)

ALPHA 5 DISINTEGRATIONS PER MINUTE PER WIPE BETA 14 DISINTEGRATIONS PER MINUTE PER WIPE l

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TABLE 2 INSTRUMENTATION SURVEY KIT #6 NRC TAG 046945

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LUDLUM 2241-2 RATE METER / SCALER SN 132192 LUDLUM 44-9 PANCAKE PROBE SN PR110149 l l

LUDLUM MODEL 3 RATE METER SN 053003 WITH 44-9 PROBE LUDLUM MODEL 19 MICRO R METER SN 011021 THE ABOVE LISTED INSTRUMENTS WERE WITHIN THEIR CALIBRATION CYCLE AT THE TIME OF THE INSPECTION i

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