ML20044C454
| ML20044C454 | |
| Person / Time | |
|---|---|
| Site: | 07000371 |
| Issue date: | 01/15/1993 |
| From: | Jaberaboansari OAK RIDGE NATIONAL LABORATORY |
| To: | Roth J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20044C438 | List: |
| References | |
| NUDOCS 9303230057 | |
| Download: ML20044C454 (8) | |
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January 15, 1993 i
j Mr. Jerome Roth
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Region 1 U.S. Nuclear Regulatory Commission j
475 Allendale Road King of Prussia, PA 19406
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SUIUECT:
CONFIRMATORY RADIOLOGICAL SURVEY PLAN FOR UNC NAVAL PRODUCTS, UNAFFECTED. INDOOR-AREAS (BOOK 4), MONTVILLE, j
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Dear Mr. Roth:
.j Enclosed is a copy of the subject document. Per our earlier conversadon, on-site activities have
-j been scheduled for February 8-12, 1993. If there are any questions, please direct them to.me ~
at (615) 576-3305 or Michele Landis at (615) 576-2908.
i Sincerely, j
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Armin Jaberaboansari l
Project Leader
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- Environmental Survey 1
and Site Assessment Program AJ:mkp jl Enclosure
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- cc:
L Parrott, NRC/NMSS, 1!
< 3 T. Mo, NRC/NMSS,-
1j D. Tiktinsky, NRC/NMSS, _
J. Swift /F. Brown, NRC/NMSS.,
j
.- J.' Kinneman, NRC/ Region I
- j M. Landis, ORISE j
- J. Berger, ORISE j
- A. Payne, ORISE j
PMDA:
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- File 9303230057 930312' iPDR. ADOCK 07000371-1 C.'
PDR P. O. BOX U7. OAK R DGE, TENNESSEE 3783 00117 -
7 manageTsd Waled by Ook Ridge Associo4d Un1versit es for the U's. Department of Energy ll n
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1 CONFIRA1ATORY SURVEY PLAN FOR TIIE UNAFFECTED INDOOR AREAS, UNC NAVAL PRODUCTS MONTVILLE, CONNECTICUT SITE IIISTORY AND DESCRIPTION United Nuclear Corporation (UNC) Naval Products fabricated reactor fuel elements for the Naval Reactors program at the Montville, Connecticut facility under U. S. Nuclear Regulatory -
Commission (NRC) License SNM-368. The license authorized the fabrication and inspection of unclad fuel components, encapsulation of the fuel into corrosion-resistant materials, assemblage of these into larger components or into reactor cores and laboratory operations -
necessary to support these operations. The radioactive materials utilized were fully enriched unitradiated uranium and uranium source materials. In March of 1990, UNC was notified by.
the U. S. Government that certain contracts were being terminated. As a result of that action, UNC decided to initiate decontamination and decommissioning efforts at the UNC facility in the -
summer of 1990, while concurrently completing work on existing contracts.
l The Montville facility was built in 1957-59, with small additions in 1961 and 1966. A major expansion, Building M was completed in 1969. All operations in these areas were limited to clad fuel. Following authorization by the Atomic Energy Commission (predecessor to NRC)in 1972, UNC constructed four additional buildings. Building A was completed in early 1973.
i Operations in Building A were also limited to clad fuel.
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Building B was completed in September of 1973 and was used for the initial' forming and encapsulation of uranium-bearing material. Building C was completed in May 1973 and contained the main office and clerical support staff. Buildings D, R, S and T were used for i
Prepared by the Environmental Survey and Site Assessment Program of Oak Ridge Institute for -
Science and Education, Oak Ridge, TN, under interagency agreement (NRC Fin. No. A-9076) between the U.S. Nuclear Regulatory Commission and the U.S. Depanment of Energy.
January 14, 1993 l
7 UNC Mantville. January 12.1993
.e, inspection and bulk storage of non-uranium bearing materials. Construction of Building L was completed in 1990, however, installation of uranium processing equipment was never completed.
The 251 acre UNC site is located in the northeast corner of the town of Montville, New London -
County, Connecticut. Only a small portion of the site is occupied by the UNC facility. The Central Vermont Railroad has a right-of-way along the Thames River at the eastern edge of the UNC site. The plant is served by a spur from the railroad and has car and truck access from State Highway 32. The site is bounded on the north by the Thames River, on the east by the railroad and the Thames River, and on the south and west by private propeny.
i The plant buildings are set in the side of the valley with the roof line' nearly level with the' parking lot. A security fence surrounds the building complex. About 24,400 m is devoted to 2
manufacturing operations, with the remainder used for offices, pollution control facilities and storage. Exterior walls of all buildings are a combination of concrete block and insulated metal
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siding.
.f Decontamination, final licensee survey, and confirmatory activities have been completed for Unit l
1, Unit 2, Unit 3 Vault, Pack Assembly, Septic Fields 1 and 2, Incinerator Pad, and Building.
i B-South. UNC has completed the final survey for the following unaffected areas: Encapsulated -
j Material Manufacturing areas (Buildings B-North, A, M, and East Plant); Identified Incident 1
areas (Hot Roll, Warm Roll, Vapor Grit Blast, and Welding.Atea); Office areas, Mezzanines, and new MFP Facility; and Support Building (D, R., S, T, H Buildings, Carpentry Building,.
Compressor Building, Pump House West, Security Towers, and Security Gate House). The U.S.
j Nuclear Regulatory Commission, Region 1 Office, has requested that the Environmental Sun ey.
and Site Assessment Program (ESSAP) of Oak Ridge Institute for Science and Education j
(ORISE) perform an independent confirmatory survey of these facilities.
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OBJECTIVE The objectives of the confirmatory process are to provide independent document reviews and radiological data, for use by the NRC in evaluating the adequacy and accuracy of the licensee's radiological status report, relative to established guidelines.
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RESPONSIllILITY i
i Work described in this survey plan will be performed under the direction of Michele Landis, Project Manager and Armin Jaberaboansari, Project Leader with ESSAP. The cognizant site a
supervisor has the authority to make appropriate changes to the survey procedures as deemed necessary. After consultation with the NRC site representative, the scope of the suivey may be _
altered as the suney progresses.
Deviations to the survey plan or procedures will be documented in the site log book.
1 DOCUMENT REVIEW ESSAP will review the licensee's radiological survey data. Procedures and methods utilized by the Licensee will be reviewed for adequacy and appropriateness. The data will be reviewed for accuracy, completeness, and compliance with guidelines.
PROCEDURES 7
- Survey activities will be conducted in accordance with the ORISE ESSAP Survey Procedures and Quality Assurance Manuals. Specific procedures applicable to this survey arelisted on Page 6 of this survey plan.
t UNC Montvine - January 12,199) 3
REFERENCE GRID
-i The reference grid systems established by the licensee will be utilized. Measurement locations on ungridded surfaces will be referenced to prominent building features or the existing grid.
SURFACE SCANS Surface scans will be performed using Nal scintillation and large-area gas proportional detectors, coupled to countrate meters with audible indicators. In the Manufacturing Area, approximately 10% of the floor surfaces will be scanned for gamma and alpha radiation. In the Identified f
Incident Areas, in addition to gamma and alpha floor scans, beta scans will be performed on approximately 10% of the floor surfaces. In the Offices, Mezzanines, and Support Buildings, j
only gamma scans will be performed. Particular attention will be given to scanning doorways and passage ways in and between the buildings.
SURFACE ACTIVITY MEASUREMENTS Direct measurements for total and removable alpha and beta activity will be performed at randomly selected grid line intersections (floor) and at the center of randomly selected grid blocks (lower walls). The number of these measurements in each room or building will vary between 10-25% of that provided in the licensee's final. status survey report.8 These-measurements will be performed using thin-window GM and ZnS scintillation detectors, coupled
.l to countrate meters.
EXPOSURE RATE MEASUREMENTS l
t Background exposure rates, determined from previous surveys at this site, will be used for -
comparison. Exposure rates will be measured at 1 m above the surface at approximately 30' l
locations, using a pressurized ionization chamber.
UNC Montvbe. January 11.1993 4
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SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data will be returned to ORISE's ESSAP laboratory in Oak Ridge, TN for analysis and interpretation. Smears will be analyzed for gross alpha and gross beta activity using a low background gas proportional counter, and the results will be converted to units of disintegrations per minute per 100 cm (dpm/100 cm ).
Direct measurements for surface activity will be 2
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converted to units of dpm/100 cm. Exposure rates will be reported in pR/h. The data generated will be compared with the licensce's documentation and NRC guidelines established for release to unrestricted use. Results will be presented in a report and provided to the NRC for review and comment.
GUIDELINES 2
The following surface contamination guidelines for uranium apply to all areas:
Total Activity 2
2 5,000 dpm a/100 cm, total, averaged over 1 m 2
2 15,000 dpm a/100 cm, total, maximum in 100 cm Removable Activity 2
1,000 dpm a/100 cm The exposure rate guideline is 5 pR/hr above background.2 TENTATIVE SCIIEDULE Measurement and Sampling February 8-12,1993 Sample Analysis March 1993 Draft Report June 1993 UNC Mmtville - January 12,1993 5
e LIST OF CURRENT PROCEDURES Applicable procedures from the ORISE ESSAP Survey Procedures Manual (Revision 7.;
May 31,1992) include:
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Section 5.0 Instrument Calibration and Operational Check-Out 5.1 General Information 5.2 Electronic Calibration of Ratemeters q
5.3 Gamma Scintillation Detector Check-Out and Cross-Calibration 5.4 Alpha Scintillation Detector Calibration and Check-Out 5.5' GM Detector Calibration and Check-Out-5.6 Proportional Detector Calibration and Check-Out f
5.7 Pressurized Ionization Chamber Calibration and Check-Out 5.9-Floor Monitor Check-Out
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5.13 Field Measuring Tape Calibration Section 6.0 Site Preparation 6.2 Reference Grid System Section 7.0 Scanning and Measurement Techniques 7.1 Surface Scanning 7.3 Alpha Radiation Measurement 7.4 Beta Radiation Measurement n'
7.5 Gamma Radiation (Exposure Rate) Measurement ri Section 9.0 Integrated Survey Procedures 9.2-General Survey Approaches and Strategies.
f.i Section 10.0 Health and Safety Control of Cross Contamination Section 11.0 -
Quality Assurance and Quality Control i
UNC Montvik. January 12,1993 6
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t REFERENCES F
1.
UNC Naval Products, Final Decontamination and Decommissioning Surveys, Book 4, Montville, CT, December 1992.
2.
U.S. Nuclear Regulatory Commission, Division of Fuel Cycle and Material Safety, Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of Licenses for Byproduct, Source or Special Nuclear Material, Washington D.C., August 1987.
3.
ILS. Nuclear Regulatory Commission, Office of Nuclear Safety and Safeguards, Review Plan: Evaluating Decommissioning Plans' for Licensees Under 10 CFR Parts 30,40, and 70, Washington, D.C.,1991.
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UNC Entville. January 12,1993 7
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