ML20202F746
| ML20202F746 | |
| Person / Time | |
|---|---|
| Site: | 07000133 |
| Issue date: | 02/12/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20202F743 | List: |
| References | |
| 70-0133-98-01, 70-133-98-1, NUDOCS 9802190290 | |
| Download: ML20202F746 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION REGION lli Docket No: 070-00133 (Terminated)
License Nos: SNM 183 (Terminated)
C 3892: C 3790 (Terminated) l 34-00653 01/02 (Terminated)
Report No: 070-00133/98001(DNMS)
Former Licensee: Clevite Corporation
$40 East 105th Street Cleveland, OH 44108 Inspection Dates: January 1415,1998 January 22,1998 Location: Shorebank Enterprise Group 540 East 105th Street Cleveland, OH 44108 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 Decommistioning Branch Division of Nuclear Materials Safety 9002190290 900212 PDR ADOCK 07000133 C PDR
EXECUTIVE
SUMMARY
FORMER CLEVITE FACILITY
- inspection Report 070 00133/98001(DNM8)
This was a special announced inspection to perform a radiological confirmatory survey of the
- enclosed weld shop room. The purpose of the survey was to determine if the remediation l contractor's final survey data accurately reflected the condition of the area and met NRC unrestricted use guidelines. The contractor's Final Status Survey Plan (FSP) was review 9d and surveys were performed in an area (machine shop) where the remediation contractor was performing a final survey.
Confirmatory survey resutis of the weld shop and machine shop did not identify any residual l radioactive materialin exce% of the NRC's unrestricted use guidelines for enriched uranium or thorium. The contractor ' nad implemented the FSP adequately.
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Resort Details
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.e ,c Special Nuclear Material Lloense No. SNM 183 was issued to Clovite Research Center, Division of Clovite Corporation on Merch 10,1958. This license authorized the use and possession of enriched uranium (EU) at its facility located at 540 East 106th Street in Cleveland, Ohio. The licensed activitier Included molting, alloying, forging, rolling, welding, pickling, machining, stamping, sintering, and chemkal and metallographic l analyses of EU powder and ceramic materials for the production and fabrication of fuel .i
, elements for nuclear reactors. The license initially authorized about 9 kilograms (kgs) of l
. 90% EU, and subsequent amendments raised this authorization to nearly 56 kos. An ^
- area on the first floor in the rear of the building was reserved for fuel fabrication.
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3 - Other research activities, covered under Source Material License Nos. C 3790 and j C 3692, authortred about 90 kgs of natural uranium and 5 grams of thorium sulfide,. ;
l respectively. ;
I' ' Gould, Inc., the successor of Clovite Corporation, contracted with Sevenson . ;
} Environmental services, Inc., (Sevenson) to develop and implement a remediation/ survey ;
j plan to render the property fit for release for unrestricted use. The contractor submitted 3 j the Site Characterization Survey / Termination Survey, Remediation, and Heelth and e l Safety Plan on May 10,- 1995, and was authorized by NRC to proceed with site 1 j characterization in a letter dated June 1,1995. The site characterization, remediation i l and final surveys have been completed. !
! i i Sevenson submitted the Final Status Survey Plan (FSP) to the NRC on November 24, j 1997. The FSP was approved by NRC on December 12,1997 Previous inspections 1 have verified that the responsible party has conducted remediation activities in accordance with its approved Remediation Plan.
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, On January 1415,1998, NRC personnel accompanied by a representative from the Ohio 1 i Department of Health, Bureau of Radiation Protection, conducted an inspection at the !
former Clovite Corporation facility site. The scope of the inspectbn was limited to; ;
(1) evaluating final survey activities in the West wing of the facility, and . .
(2) conducting a confirmatory survey in the West wing wild shop to determine if that --
room would meet the NRC release criteria defined in Guidelines for Decontamination of Facilities and Eautoment prior to Release for Unrestricted Use or Termination of Licenses i for Bvoroduct. Source. or Special Nuclear Material. dated Auaust.1987.
2.0 c inannotion Activities 2.1 Observation of Final Survey Activities in West Wino and Review of Contractor Quality ,
Assurance Pronram 2.1.1 S. gent
. The inspectors observed Sevenson's in process final survey activities in Room 16 of the West Wing and reviewed quality control documents to determine if the NRC approved
~ FSP was being implemented.
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l 2.1.2 Observations and Findinas The inspectors observed Sevensen radiation technicians (RTs) conducting final surveys and direct measurements in the machine shop (Room 16) of the West Wing. The inspectors also conducted random surveys of Room 16 and discussed survey resuNs with Sevensen RTs. The following *wmentation was reviewed:-
1, Scale drowings of Room 16 < wing survey grids, and area classification (affected/ unaffected).
- 2. Training records for Sevenson's Health Physica Manager, and Health Physics Technicians in charge of conducting the final survey at the facility.
- 3. - Calibration records for final survey instrumeits, o _ The inspectors reviewed the quellfications, and training records of Sevensos) personnel 1 who were conducting the final survey. The Inspectors determined that all personnel had tooelved; (1) OSHA 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> training, and (2) Sevenson training for on sito personnel, as required by the approved Health and Safety Plan. Interviews with Sevenson personnel indicated that they understood radiological controls and were aware of their responsibilities in the area of radiation protection.
The inspectors examined Sevenson's organization, operational procedures, document ;
control / records management, and equipment maintenance and control. Sevenson's i organizational structure is consistent with Section 4.2 of the FSP. Records documenting quality affecting activities were prepared and were retrievable for inspection.
The quality assurance program for field survey instrumentation and laboratory counting systems was evaluated. Calibration records for final survey and laboratory instruments
- Indicated that all instruments in use had been calibrated within six months, using NIST traceable standards, as required by the approved FSP in addition, Sevenson's recorcis also indicated that operational and background checks were conducted on survey instruments once during each four hours of instrument use, as required.
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Conclusions:
Based on observations of in process activities, discussions with Sevenson personnel, reviews 9f Sevenson personnel quellfications, and quality control documentation, Sevenson was effectively implementing the approved FSP for the final survey.
- 2.2 Gepfirmatory Survev in West Wina Wald Shoo 2.2.1 Scope The NRC inspectors conducted a confirmatory survey in the weld shop, located in the west wing. This survey consisted of performing independent scan surveys and collecting smears to determine the presence of fixed and removable contamination.
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i 2.2.2 Observations and Findinot !
l The inspectors performed a scan survey of the weld shop floors and walls using Ludlum ;
Model 3 and Model 12 rate meters and a Ludlum Model 22412 rate meter / scaler, all equlpped with Ludlum Model 44 9 pancake probes. The surveys emphasized crevices, wall / floor junctions, drain areas, overhead horizontal surfaces, fan blades and vertical louvers (air exhaust). Direct survey measurements were conducted for beta / gamma radiation. Readings on the wood floor ranged from 40 00 cpm, while readings on the walls, composed of cinder block, glass, and dry wall, ranged from 60 80 cpm. These readings were consistent with background measurements.
A total of 25 wipe samples were collected from the floor, walls, and windows to determine if removable contamination was present above the NRC retcase guidelines. A one minute count was taken at each sample location. 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.
2.2.3 Conclusions Data from direct measurement and wipe samples indicated that radioactivity was within the NRC release guidelines. All survey measurements were consistent with background readings. Analysis of the wipes showed that no residualloose radioactive materialwas present and activity levels were consistm with background levels and thus were well below NRC release guidelines for unrr ed use.
3.0 Exit Meetina At the conclusion of the inspection on January 15,1998, the preliminary results of the inspection were discussed with the Individuals identified in this report. None of the information provided during the inspection was indicated to be proprietary.
On January 23, based on the results of analyses of the wipe samples, the NRC Division of Waste Management issued a letter to Mr. James F. Cronmiller, Gould Electronics Inc.,
relsasing the Wek Shop for unrestricted use.
pef.pns Contacted Mr. Kim W. Lickfield Mr. James Cronmiller Project Manager Gould Electronics, Inc.
Sevenson Environmental Services Mr. .lohn Schoeniger Mr. Timothy Colgazier Shorebank Enterprise Group Site Manager Sevenson Environmental Services Mr. Rory Grub.
Radiation Safety Officer Sevenson Environmental Services
Attachment:
Table 1 5
TABLE 1 SAMPLE DESCRIPTION MATERIAL DPM i WALL GRID L 15 BRICK <MDA 2 FLOOR GRID G 9 WOOD <MDA 3 FLOOR GRID J 8 CONCRETE <MDA 4 FLOOR GRID K 8 CONCRETE <MDA 5 FLOOR GRID L 10 CONCRETE <MDA 6 FLOOR GRID M 8 CONCRETE <MDA
- 7 FLOOR GRID N 9 CONCRETE <MDA 8 FLOOR GRID M 11 CONCRETE <MDA 9 FLOOR GRID N 11 CONCRETE <MDA 10 FLOOR GRID M 11 CONCRETE <MDA 11 FLOOR GRID M 14 WOOD <MDA 12 FLOOR GRID L 14 WOOD <MDA 13 FLOOR GRID H 13 WOOD <MDA 14 FLOOR GRID J 11 WOOD <MDA 15 FLOOR GRID F 13 WOOD <MDA 16 FLOOR GRID H 11 WOOD <MDA 17 FLOOR GRID F 11 WOOD <MDA 18 HALL GRID E 11 CONCRETE <MDA 19 WALL GRID C-7 DRYWALL <MDA 20 WALL GRID C 12 DRYWALL <MDA 21 WALL GRID G 16 BRICK <MDA 22 WALL GRID H-16 BRICK <MDA 23 WINDOW GRID Q 10 GLASS <MDA 24 WALL GRID P 7 BRICK <MDA 25 WALL CORNER GRID E 17 BRICK <MDA MINIMUM DETECTABLE ACTIVITY (MDA)
ALPHA 5 DISINTEGRATIONS PER MINUTE (DPM) PER WIPE BETA 14 DISINTEGRATIONS PER MINUTE (DPM) PER WIPE
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