ML20235E218
| ML20235E218 | |
| Person / Time | |
|---|---|
| Site: | Framatome ANP Richland |
| Issue date: | 05/31/1987 |
| From: | Deming E OAK RIDGE ASSOCIATED UNIVERSITIES |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20235E216 | List: |
| References | |
| CON-FIN-A-9076-3 NUDOCS 8707100460 | |
| Download: ML20235E218 (34) | |
Text
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E Prepared by Oak Ridge Assoc lated CONFIRMATORY SURVEY Universities Prepared for OF THE U.S. Nuclear Regulatory commission s CENTRIFUGE TEST FACILITY Region V Office Supported by ADVANCED NUCLEAR FUELS CORPORATION Safeguards and
"",t'1".ls Programs RICHLAND, WASHINGTON n
Division of Inspection Programs; Office of E. J. DEMING Inspection and Enforcement l
Radiological Site Assessment Program Manpower Education, Research, and Training Division FINAL REPORT MAY 1987 hDR 7
D R
1
4 CONFIRMATORY SURVEY OF THE CENTRIFUGE TEST FACILITY ADVANCED NUCLEAR FUELS CORPORATION RICHLAND, WASHINGTON Prepared by E.J. DEMING Radiological Site Assessment Program Manpower Education, Research, and Training Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff J.D. Berger A.S. Masvidal R.D. Condra C.L. Murphy M.R. Dunsmore C.F. Weaver R.C. Gosslee B.C. Williams Prepared for Safeguards & Materials Progr.sms 3 ranch Division of Inspection Programs Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region V Office Final Report May 1987 This report is based on work performed under Interagency Agreement DOE No. 40-816-8 3 NRC Fin. No. A-9076-3 between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy. Oak Ridge Associated Universities performs complementary work under contract number DE-AC05-760R00033 with the U. S. Department of Energy.
TABLE OF CONTENTS i
Page List of Figures 11 List of Tables iii Introduction 1
I Site Description I
Survey Procedures 2
ReSultS d
Comparison of Results with Guidelines 5
5 Summary.
Appendices Appendix A: Major Sampling and Analytical Equipment Appendix B:
Analytical Procedures Appendix C: Guidelines for Decontamin" tion of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source, or Special Nuclear Material 1
LIST OF FIGURES Page FIGURE 1:
Exterior View of the Centrifuge Test Facility, Advanced Nuclear Fuels 6
FIGURE 2:
CTF Plan View Indicating Floor Elevations and Room Locations.
7 FIGURE 3:
Plan View of the Control Room (elevation 38 m) Indicating Grid System Established for Survey Reference and Grid Blocks Selected for Survey.
8 FIGURE 4: Location of Grid Blocks Selected for Survey on the Subfloor of the Control Roon.
9 FIGURE 5: Locations for Total and Removable Contamination Measurements on Upper Walls and Ceiling of the Control Room 10 FIGURE 6:
Plan View of the Centrifuge Pit Area, (level 1 through level 3), Indicating Grid Established on Floor and Lower Walls, Grid Blocks Selected for Survey, and Location of Random Wall Measurements 11 FIGURE 7:
Plan View of the CTF at Level 4.
12 FIGURE 8: Location of Single Point Measurements for Total and Removable Contamination on the Walls Between Centrifuge Pit Area Levels 4and5..........................13 FIGURE 9:
Plan View of the CTF at Level 6..
14 FIGURE 10: Location of Total and Removable Contamination Measurements on the Walls from Level 6 to the High Bay Ceiling.
15
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11
LIST OF TABLES Page TABLE 1:
Summary of Surf aca Contamination Measurements 16 TABLE 2: Uranium 238 Concentrations in Residue Samples 18 e
s iii
y.
CONFIRMATORY SURVEY OF THE CENTRIFUCE TEST FACILITY ADVANCED NUCLEAR FUELS CORPORATION RICHLAND, WASHINGTON INTRODUCTION From 1976 to 1979, the Centrifuge Test Facility was operated by the Exxon Nuclear Company, now known as the Advanced Nuclear Fuels Corporation (ANF), in Richland, Washington.
The facility was licensed by the Nuclear Regulatory Commission (NRC),
(license
- ShH-1227) to mechanically test centrifuge enrichment equipment with UF6 gas.
During testing four hundred grams of UF 6 were introduced into a single centrifuge; the UF6 was then trapped and reused. A total of 2 kilograms of natural UF6 was used at the Centrifuge Test Facility from 1976 to 1979.
Small containers of enriched UF6 were also used to calibrate a mass spectrophotoneter which was housed in the CTF.
Additional UF6 gas sampling was carried out in an open faced hood used for analytical work. At the termination of the project in 1979, the majority of the equipment, including the centrifuges, hood, piping, and ductwork, was removed and the building was decontaminated and surveyed by ANF personnel.
Advanced Nuclear Fuels has requested termination of NRC licensing for the Centrifuge Test Facility.
At the request of the NRC, Region V, the Radiological Site Assessment Program of Oak Ridge Associated Universities (ORAU),
Oak Ridge, TN, conducted a confirmatory radiological survey during January 13-22, 1987. The findings of that survey are presented in this report.
SITE DESCRIPTION The ANF plant is located on Horn Rapids Road, approximately 2 km north of Richland, Washington. The Centrifuge Test Facility is a separate building, 0.5 km to the east of the main ANF plant.
The building consists of a large bay area (18 m x 11 m x 15 m); the centrifuge pit area (12 m x 6 m x 56 m), which contained 3 centrifuges and was divided into 6 levels with grated flooring; a control room, which contained an open faced hood and mass spectrophotometer; a conference room; several offices; and a maintenance room (Figures 1 and 2).
1
SURVEY PROCEDURES Obj ect ives The objectives of the survey were to verify the adequacy and accuracy of the licensee's survey and to confirm the radiological conditions, relative to the NRC guidelines for release of facilities for unrestricted use.
Procedures Document Review ORAU reviewed the decontamination plan and final radiological survey report, prepared by ANF.
Facility Survey Gridding A 1.2 m x 1.2 m grid system was established on the floor and lower walls and in the subfloor space of the control room, based on the size of the existing floor squares. A 1 m x 1 m grid was established on the floor and lower walls of the basement areas beneath the centrifuges.
Other surface areas were not gridded; however survey activities were referenced to existing building features.
Surface Scans To identify possible locations of residual contamination,
- thorough, systematic surf ace scans were performed.
All building floors were scanned for elevated alpha, beta, and gamma levels using an alpha / beta proportional floor monitor and NaI(T1) gamma scintillation detectors with audibly indicating scaler /ratemeters.
Lower walls (up to 2 m) were scanned using " pancake" GM detectors and ZnS alpha detectors.
Representative overhead surfaces (above 2 m) such as ledges, girders, ductwork, and miscellaneous equipment were also scanned.
2
A walkover gamma scan of outside areas, to 20 m beyond the facility fenceline, was performed using Nal(TI) scintillation detectors.
Measurement of Surface Contamination Levels Thirty-three grid blocks on the floor, subfloor, and lower walls in the control room and 21 grid blocks from the centrifuge pit area (lower level) were randomly selected for surface contamination measurements.
Total measurements of alpha and beta gamma contamination levels were systematically performed at the center and four points midway between the center and block corners.
Smears for removable alpha contamination were performed at the location in each grid block with the highest direct alpha measurement.
Total and removable contamination levels were also measured at 129 other locations on the building floors, walls, ceilings, roof, and miscellaneous objects.
Exposure Rate Measurements Gamma exposure rates at 1 m above the floor were measured at 21 locations throughout the Centrifuge Test Facility using a NaI(T1) gamma scintillation detector, cross calibrated with a pressurized ionization chamber.
Miscellaneous Sampling Eleven samples of residue, which had accumulated on bay and test pit area 2
rafters, were collected from 100 cm areas.
Sample Analysis and Interpretation of Results Staears obtained for the determination of removable alpha contamination were analyzed for gross alpha activity. Residue sampics were analyzed for gross alpha
- activity, and U-23S concentrations were determined by neutron activation analyses.
Additional information concerning major instrumentation, sampling equipment, and analytical procedures is provided in Appendices A and B.
Results were compared with NRC guidelines, established for release of facilities for unrestricted use (Appendix C).
3
RESULTS Document Review In general, the decontamination plan appears to be adequately developed and implemented to ensure the NRC guidelines were met, and the final survey report adequately summarized the radiological status of the site.
Residual contamination levels identified in this report were within the established NRC guidelines for decommissioning.
No significant discrepancies were identified in the documents reviewed.
Surface Scans No locations of elevated alpha, beta, or gamma radiation levels were identified on building surfaces or around the outside of the building.
Surface Contamination Measurements Results of total and removable contamination measurements are summarized in Table 1.
Alpha and beta-gamma levels were, for the most part, less than the minimum detectable activity.
The maximum alpha and beta-gamma levels were 2
2 590 dpm/100 cm and 1200 dpm/100 cm, respectively, measured at one isolated location on the main floor of the bay area.
The maximum removable alpha 2
contamination level was 17 dpm/100 cm,
Exposure Rate Measurements Exposure rates measured throughout the facility ranged from 5 to 8 pR/h.
Miscellaneous Measurements Uranium 238 concentrations in residue samples collected from the rafter surf aces are presented in Table 2.
These samples contained U-238 concentrations 2
ranging from 1 to 41 dpm/100 cm,
4
COMPARISON OF RESULTS WITH GUIDELINES The Nuclear Regulatory Commission's uranium surface contamination guidelines are:
Total Contamination 15000a dpm/100 cm2 (maximum in a 100 cm area) 2 5000a dpm/100 cm2 (averaged over 1 m )
2 Removable Contamination 2
1000a dpm/100 cm
\\
Residual contamination levels measured during this survey were all well within these guidelines.
SUMMARY
On January 13-22, 1987, ORAU performed a confirmatory survey of the Centrifuge Test Facility at the Advanced Nuclear Fuels Corporation Site in Richland, Washington.
The survey included surf ace alpha, beta and gamma scans, measurement of total and removable contamination levels, and the measurement of U-238 concentrations in residue samples.
The findings support the close-out survey performed by the licensee, and confirm that the radiological conditions satisfy the NRC guidelines, established for release for unrestricted use.
5
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4 TABLE 2 URANIUM 238 CONCENTRATIONS IN RESIDUE SAMPLES ADVANCED NUCLEAR FUEL CORPORATION RICHLAND, WASHINGTON U-238 Leveg Sample ID Sampling Location (dpm/100 cm )
1 Rafter - Level 3 - West Side 12 2
Raf ter - Level 4 - North Side 1
3 Rafter - Level 4 - North Side 6
4 Raf ter - Level 5 - East Side 2
5 Rafter - Level 6 - North Side 2
6 Raf ter - Level 7 - West Side 2
7 Rafter - Level 9 - West Side 15 8
Raf ter - Level 9 - East Side 41 9
Rafter - Level 7 - East Side 25 10 Raf ter - Level 8 - South Side 19 11 Rafter - Level 8 - North Side 33 18
e
'h APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT l
l
APPENDIX A MAJOR SAMPLING AND ANALYTICAL EQUIPMENT The display or description of a specific product is not to be construed as an endorsement of that product or its manufac'urer by the authors or their employer.
A.
Direct Radiation Measurements Eberline " RASCAL" Portable Ratemeter-Scaler Model PRS-1 (Eberline, Sante Fe, NM)
Eberline PRM-6 Portable Ratemeter (Eberline, Sante Fe, NM)
Ludlum Alpha-Beta Floor Monitor Model 239-1 (Ludium, Sweetwater, TX)
Ludlum Ratemeter-Scaler Model 2220 (Ludlum, Sweetwater, TX)
Eberline Alpha Scintillation Probe Model AC-3-7 (Eberline, Sante 7e, NM)
Eberline GM " Pancake" Probe Model HP-260 (Eberline, Sante Fe, NM)
Eberline Scintillation Alpha Counter Model SAC-4 (Eberline, Sante Fe, NM)
Victoreen NaI Gamma Scintillation Probe Model 489-55 (Victoreen, Inc., Cleveland, OH)
Reuter-Stokes Pressurized Ionization Chamber Model RSS-Ill (Reuter-Stokes, Cleveland, OH)
A-1
B.
Laboratory Analyses Automatic low-background Alpha-Beta Counter Model LB5110-2080 (Tennelec, Inc., Oak Ridge, TN)
Alpha Spectrometry System Tennelec Electronics (Tennelec, Oak Ridge, TN)
Surface barrier detectors (EG6G ORTEC, Oak Ridge, TN)
Multichannel Analyzer Model ND-66 (Nuclear Data. Schaumburg, IL)
Californium-252 Sougce 2
30 mg, flux: 2 x 10 n/cm - sec (Oak Ridge National Laboratory, Oak Ridge, TN) l I
A-2
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APPENDIX B MEASUREMENT AND ANALYTICAL PROCEDURES I
APPENDIX B Measurement and Analytical Procedures Alpha and Beta-Gamma Measurements Floors were scanned for elevated alpha levels by passing slowly over the surface with a Ludlum Model 239-1 Alpha / Beta Gas Proportional Floor Monitor.
Other surfaces were scanned using Victoreen Model 489-55 gamma scintillation probes containing 3.2 cm x 3.8 cm NaI(T1) scintillation crystals, Eberline Model AC3-7 alpha scintillation probes, and Model HP-260 thin-window pancake GM probes with Eberline Model PRS-1 portable scaler /ratemeters.
Measurements of total alpha radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model AC3-7 alpha scintillation probes.
Measurement of direct beta-gamma radiation levels were performed using Eberline Model PRS-1 portable scaler /ratemeters with Model HP-260 thin-window pancake GM probes.
Count rates (cpm) were converted to disintegration rates 2
(dpm/100 cm ) by dividing the net rate by the 4n efficiency and correcting for 2
active area of the detector.
The effective window area was 59 cm for the alpha 2
detectors and 15 cm for the GM detectors. The average background count rate was approximately 2 cpm for the alpha probes and 40 cpm for the GM probes.
Removable Contamination Measurements Smear measurements were performed on numbered filter paper disks, 47 mm in diameter.
Smears were placed in labeled envelopes with the location and other pertinent information recorded.
A ZnS alpha scintillation counting system was used to evaluate individual smears at the site; smears were recounted on a low background proportional counter at the Oak Ridge laboratory.
Analysis of Miscellaneous Residue Samples for Uranium-238 Samples were analyzed by neutron activation analysis by exposing them to a Californium-252 radiation source for 15 to 30 minutes.
Solid state gamma detectors were then used to determine U-239 content and relate that value to the total sample U-238 concentration.
B-1
Exposure Rate Measurements Measurements of gamma exposure rates were performed using an Eberline PRM-6 portable ratemeter with a Victorcen Model 489-55 gamma scintillation probe containing a 3.2 cm x 3.8 cm NaI(T1) scintillation crystal.
Count rates were converted to exposure rates (pR/h) by cross-calibrating with a Reuter Stokes model RSS-Ill pressurized ionization chamber.
(
Errors and Detection Limits The uncertainties associated with the analytical data, presented in the tables of this report, represent the 95% (20) confidence levels based only on counting statistics.
Other sources of error associated with the sampling and analyses introduce an additional uncertainty of i 6 to 10% in the results.
Calibration and Quality Assurance Laboratory and field survey procedures are documented in anuals developed specifically for the Oak Ridge Associated Universities' Radiological Site Assessment Program.
Instruments were calibrated with NBS-traceable standards.
Quality control procedures on all instruments included daily background and check-source measurements to confirm equipment operation within acceptable statistical fluctuations.
The ORAU laboratory participates in the EPA and EML Quality Assurance Program.
B-2
e APPENDIX C GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL I
e GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE OR SPECIAL NUCLEAR MATERIAL l
U.S. Nuclear Regulatory Commission Division of Fuel Cycle & Material Safety Vashington, D.C.
20555 July 1982
The instructions in this guide, in conjunction with Table 1,
specify the radionuclides and radiation exposure rate limits which should be used in decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use.
The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use nay be different. The release of such facilities or items from regulatory control is considered on case-by-case basis.
1.
The licensee shall make a
reasonable effort to eliminate residual contamination.
2.
Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination
- levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the application of the coyering.
A reasonable effort must be made to minimize the contamination prior to use of any covering.
3.
The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these locations is likely to be representative of contamination on the interior of the pipes, drain lines, or ductwork.
Surfaces or premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes of measurement shall be presumed to be contaminated in excess of the limits.
4.
Upon request, the Commission may authorize a licensee to relinquish possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified.
This nay include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status.
Such requests must:
a.
Provide
- detailed, specific information describing the
- premises, equipment or scrap, radioactive contaminants, and the nature, extent, and degree of residual surface contamination.
b.
Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
5.
Prior to release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1.
A copy of C-2
the survey report shall be filed with the Division of Fuel Cycle and Material Safety, USNRC, Washington, D.C.
20555, and also the Administrator of the NRC Regional Of fice having jurisdiction.
The report should be filed at least 30 days prior to the planned date of abandonment.
They survey report shall:
a.
Identify the premises.
b.
Show that reasonable effort has been made to eliminate residual contamination.
c.
Describe the scope of the survey and general procedures followed.
d.
State the findings of the survey in units specified in the instruction.
Following review of the report, the NRC will consider visiting the facilities to confirm the survey.
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