IR 05000013/1987001

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Insp Rept 50-013/87-01 on 870917-21.No Violations or Deviations Noted.Major Areas Inspected:Review of NRC Contractor Final Rept of Confirmatory Survey of Facility Decommissioning & of Records of Fuel Disposition
ML20235K294
Person / Time
Site: Lynchburg Research Center
Issue date: 09/24/1987
From: Hosey C, Revsin B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20235K282 List:
References
50-013-87-01, 50-13-87-1, NUDOCS 8710050036
Download: ML20235K294 (3)


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%*****/ SEP 2 9 G87 Report No.: 50-013/87-01 Licensee: Babcuck and Wilcox Comany  !

Lynchburg, VA 24505 Docket No.: 50-013 License flo.: CX-10 Facility Name: Lynchburg Research Center Inspection Conducted: S tember 17-21, 1987 Inspector: .

B. K. Revsin bfkd b Ddte Sigded Approved by: s W 7!Ly/}7 C. M. Hose)', Secti n Chief Date Sighed Division of Radiat on Safety and Safeguards SUMMARY Scope: This special, in-office inspection was conducted to review the NRC contractor's final report of the confirmatory survey of the decommissioning of the CX-10 reactor facilit Records of fuel dispostion, supplied by the licensee were also examine Results: No violations or deviations were identifie PDR ADOCK 05000013 0 PDR

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l REPORT DETAILS l Personnel Contacted Licensee Employee  !

R. L. Bennett, Manager, Safety and Licensing A. F. Olsen, Senior Licensing Administrator  !

Other Organization Oak Ridge Asscciated Universities (0RAU) Exit Interview The inspection scope and findings were summarized on September 21, 1987, during a telephone conversation between B. K. Revsin of the NRC Region II office and A. F. Olsen of your staf The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector during this inspectio . Closecut Inspection and Survey (83890) Confirmatory Surveys The NRC contracted with ORAU to perform a survey to confirm the survey data contained in the licensee's final report for unconditional release of the CX-10 facilit On July 14-25, 1986, ORAU performed a confirmatory radiological survey of the CX-10 area of Building A at B&W LRC. The survey included surface alpha, gamma, and beta-gamma scans, measurement of direct and removable contamination levels, and the measurement of radionuclides in soil, gravel, water and paint samples. The measurements performed by ORAU over statistically representative areas of the facility support the close-out survey performed by the licensee, i.e., residual radioactivity in the facility is less than the guidelines specified in Regulatory Guide 1.86, Table 1 and less than 5 microroentgen per hour at one meter. Consequently, the licensee has met the stipulated criteria for release of the facility for unrestricted use. A copy of ORAU's confirmatory survey issued in Final Report form in May 1987, is appended as Appendix Disposition of Special Nuclear Fuels The CX-10 reactor was licensed January 27, 1958, and used low enriched fuel, Reactor operations ceased in September 198 Reactor fuel was sent to the Department of Energy, Oak Ridge, Tennessee via 11 shipments late in 1984 and one final shipment in January 198 The inspector reviewed DOE /NRC Form 741, Nuclear Material Transaction

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k Report, and verified that the transfer of material via the above 12 shipments had been completed, Exposure Records Records of personnel exposures attributable to activities associated-with the CX-10 license were maintained by the licensee who has continuing record keeping responsibilities for personnel exposures under other NRC licenses. The licensee will continue to maintain these record . Conclusion The licensee survey.results showed no detectable contamination above the levels specified by Table 1, Regulatory Guide 1.86 or greater than 5 microroentgen per hour at one meter. Representative surveys performed by NRC contractor, ORAU, confirmed that the radiological conditions of the CX-10 portion of Building A satisfy NRC guidelines established for release of the facility for unrestricted us i

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