IR 05000375/1987001
| ML20204D456 | |
| Person / Time | |
|---|---|
| Site: | 05000375 |
| Issue date: | 03/13/1987 |
| From: | Fish R, Garcia E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20204B484 | List: |
| References | |
| 50-375-87-01, 50-375-87-1, NUDOCS 8703250501 | |
| Download: ML20204D456 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No. 50-375/87-01 Docket No. 50-375 License No. R-118 Licensee: Rocketdyne Division Rockwell International Corporation 6633 Canoga Avenue Canoga Park, California 91304 Facility Name: Rockwell International Research Reactor L-85 Inspection at: Rockwell's Field Laboratory, Santa Susana, California
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i Inspection conducted:
September 30 through October 31, 1986, and in office review February 6 through March 2, 1987.
Inspector:
S//J/87
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E. M. Garcia, Emergency Response Coordinator Date Signed Team Leader Team Members: Glen Murphy, ORAU Field Team Leader, Assistant Manager, Radiological Site Assessment Program, ORAU Dale Condra, Assistant Radiochemist, Radiological Site Assessment Program, ORAU David Gibson, Health Physics Technician, Radiological Site Assessment Program, ORAU 3[M[f 7 -
Approved By:
e R. F. Fish, Chief Date S'igned Emergency Preparedness Section Summary:
Onsite inspection on September 30 through October 2, 1986, and in office review February 6 throuah March 2,1987 of licensee submittal of February 3, 1987 and final NRC contractor report (Report No. 50-375/87-01).
Areas Inspected: This inspection consisted of an in office review of the licensee's submittal of February 3, 1987 and of the Oak Ridge Associated Universities final report on their confinnatory radiation survey of the Rockwell International Research Reactor L-85 facility. This inspection was to verify that the contamination and radiation levels required by the February
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22, 1983 Order Authorizing Dismantling of Facility and Disposition of Component Parts from the Office of Nuclear Reactor Regulation, had been satisfied. The guidance provided in Inspection Procedure 83890 was utilized.
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-2-Results: The measurements performed by ORAU confirmed the findings described in the licensee's " Radiation Survey for Release for Unrestricted Use - L-P5 Reactor Facility, Rev.sion A" (final survey report). The in office review of Rockwell's February 3, 1987 " Summary Report of Ambient Exposure Rate Measurerents at the L-85 Research Reactor Facility After Repair of Concrete Floor." indicated, that the gamma radiation levels were less than 5 micro-r per hour above background at a meter above the surface. No violations or deviations of NRC requirements were identified.
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DETAILS 1.
Persons Contacted Rockwell International
- Dr. M. E. Remley, Director, Nuclear Safety and Licensing
- Robert Tuttle. Manager, Nuclear Radiation and Nuclear Safety Vernon J. Schaubert, Manager, Nuclear Materials Management James A. Rowels, Radiation and Nuclear Safety Specialist John Moore, Radiation and Nuclear Safety Specialist Jeff A. Chapman, Radiation and Nuclear Safety Specialist State of California, Department of Health Services
- Larry R. Carter, Health Physicist Denotes those individuals present at the exit interview on October
2, 1986.
2.
Release Criteria for Unrestricted Use The radiation levels for release of the reactor facility to unrestricted use were established in the " Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Order Authorizing Dismantling of Facility and Disposition of Component Parts Rockwell International Corporation L-85 Reactor Docket No. 50-375," dated February 22, 1983. The Safety Evaluation states that surfaces must be decontaminated to levels consistent with Table 1 of Regulatory Guide 1.86, " Termination of Operating Licenses for Nuclear Reactors." Radioactive material (Co-60, Eu-152.-and Cs-137) other than surface contamination that may exist in corcrete, components, structures, and soil must be removed such that the radiation level from these nuclides is less than 5 micro-r/hr above natural background, as measured at 1 meter fron any surface or that no e
person will receive more than 10 mrem / year. Natural background is
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' defined in the Safety Evaluation as " radiation from naturally occurring radioisotopes as measured at a comparable uncontaminated structure or exterior soil surface."
3.
Independent Confinnatory Measurements The Radiological Site Assessment Program of Oak Ridge Associated Universities (0RAU), the NRC contractor, perfortred a verification radiation survey of the L-85 reactor facility, Building 1093 and surrounding area. This survey was conducted September 30 through October 2, 1986. The preliminary findings of the survey were documented on Inspection Report No. 50-375/86-01 which was issued on December 2, 1986. The survey was performed to independently verify that the release criteria for unrestricted use, described in Paragraph 2 above, was fulfilled. ORAU also reviewed all the documentation provided by the licensee in support of the licensee's radiation survey.
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The ORAU survey included:
Indoor Areas Scans of the floors and lower walls with alpha, beta and gama detectors.
Direct measurements of total and removable alpha and beta-gama contamination levels on random floor, walls, ceilings, ledges, and other horizontal and vertical surfaces locations.
Gama exposure rate measurements at 1 meter above the floor at random locations and areas of elevated gamma levels, identified by the surface scans.
Insitu gama spectrums at each location where gama exposure rate measurements were made.
Outside Areas Walkover surface scans with gama scintillation detectors, to a
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distance of 10 meters from the building in all directions.
Scans were extended to cover the access roads and parking lots
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to a distance of 80 meters from the building.
Gama spectrum analysis of surface soil samples collected in east, south, and west areas adjacent to Building T093. The area directly north of the building was covered by a small building and rock out croppings.
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Background Measurements Radiation exposure rate and gama spectra measurements of Building T453, a building outside the restricted area but of similar construction history.
Gama exposure rate measurements and gama spectra of collected.
l surface soil samples from four locations surrounding the Santa l
Susana Field Laboratory.
The survey findings indicate the total residual contamination meets the criteria for release for unrestricted use identified in Paragraph 2 above (Table 1 of Regulatory Guide 1.86). The survey also found that the radiation exposure rate criteria was fulfilled if the 10 mrom/ year value is used based on the projected occupancy rates.
The complete final ORAU report is an enclosure to this inspection report.
No violation or deviations of NRC requirements were identified.
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4.
Radiation Exposure Rate Measurements After Repair of Concrete Floor As part of the decontamination of the facility a portion of the concrete floor of Building T093 was excavated to depths ranging from 2 to 22
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inches. The licensee stated in their final survey report that this surface was not directly useable as a floor, and that a person working 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> a year at a desk adjacent to the excavated area would receive an exposure that would be less than the 10 mrem per year above background exposure cirteria. This report was reviewed and the methodology used was concurred in by NRR.
For practical use of the facility the licensee had proposed to repair the excavated floor with concrete. The licensee had committed (to NRR) to determining the radiation exposure rate after the floor repair was completed. By a letter to USNRC Region V dated February 3,1967 the licensee subnitted the results of these additional measurements.
Review of the information provided by the licensee indicates that after the repairs to the floor the maximum radiation exposure rate is below the 5 micro-r/hr above background at a meter from the floor surface.
No violations or deviations of NRC requirements were identified.
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Conclusions The evaluations and measurements made by the licensee and the NRC's contractor indicate that the criteria for release for unrestricted use has been satisfied.
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Exit Interview At the conclusion of the October 2,1986 site visit, the inspector and the ORAU Field Team Leader met with the individuals denoted in Paragraph
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The licensee was informed of the preliminary inspection findings.
The licensee was informed that no violations or deviations of NRC requirements had been identified.
It should be noted that for this inspection report no additional exit interview has been conducted.
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