IR 05000141/1979001
| ML19289F697 | |
| Person / Time | |
|---|---|
| Site: | 05000141 |
| Issue date: | 03/27/1979 |
| From: | Book H, Curtis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19289F696 | List: |
| References | |
| 50-141-79-01, 50-141-79-1, NUDOCS 7906150357 | |
| Download: ML19289F697 (3) | |
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U. S. f;UCLEAR REGULATORY COMMISSIO:I 0FFICE OF IflSPECTI0ff AfiD Ef1FORCEME.*lT REGI0fl V Report flo. 50-141/79-01 Docket flo. 50-141 License flo.
R-60 Safeguards Group Licensee:
Stanford University Stanford, California 94304
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Facility flame:
Inspection at:
Stanford, California Inspection Conducted: January 31 and March 13, 1979 Inspectors: G
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futIs 7xq /, 27 '77 Date Signdd
[.R.Curtis,RadiationSpecialist Date Signed
7 LM Approved By:
Date Signed
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[H. E. Book, Chief, Fuel Facility and Materials Safety Branch Summary:
Inspections on January 31 and March 13,1979 (Report flo. 50-141/79-01)
Areas Inspected: Announced inspection to determine the status of licensee actions being taken to effect the release of the facility that previously housed the Stanford Pool Type Research Reactor and teminate the flRC License R-60. The inspector visited the facility, observed the sampling of concrete shielding materials and observed and discussed counting, calibration, and data analysis methods.
Results: No items of compliance were identified.
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DETAILS 1.
Persons Contacted Roland Finston, Stanford University Radiation Safety Officer John Holmes, Cognizant Health Physicist, Reactor Project 2.
General Conditions The reactor facility has been deactivated; the reactor core, controls, components and support laboratory facilities have been dismantled and essentially removed from the facility. The building, Ryan Laboratory, is presently used for furniture and equipnent storage.
Extensive surveys of the facility were made in 1975 to prepare for release to unrestricted use. The only remaining radioactivity that was measured above background levels is located inside of the biological shield in the concrete floor that was immediately beneath the reactor core.
In 1976 and 1977, radiation levels of.01 to.50 mr/hr were measured above the con-crete floor and gamma spectral analysis of samples from holes drilled in this material yielded Cobalt-60 and Europium-152 in the range of.1 to 1.7 x E-4jJCi/ gram.
Incidents of vandalism and unauthorized entry into the building over the past three years have been prevalent and of concern to authorities at Stanford. The building is presently kept locked, windows, doors and any other potential access points have been boarded up and the building is subject to routine surveillance by the University security patrol.
Installation of an intrusion alarm system is presently being considered. The licensee's con-cern does not arise from consideration of any radiological hazard.
Access to the minute quantities of remaining radioactivity at the base of the inside floor of the biological shield is barred by a cover securely fastened over the top and a locked, heavy duty chain securing access via the massive moveable shield door.
Concern has been expressed over the possible liability and adverse publicity that might be associated with a case involving injury to a juvenile or other person who might gain unauthorized access to the building.
Licensee authorities are continuing their efforts to minimize the possibility of such a problem.
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Site Tour - Current Studies of Residual Activity The inspector visited the site, toured the facility, and observed the taking of three 2-inch diameter core samples of the concrete 2230 209
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floor inside the biological shield. The core samples were identified, placed in plastic bags and taken to the Health Physic's Laboratory for analysis. The. tools and personnel involved in the sampling opera-tion were monitored for contamination prior to release.
The inspector observed and discussed the core sanple analysis techniques with licensee representatives. Qualitative type measure-ments have been made on solid four inch long core segments using a 3" x 3" NaI gamma scintillation spectrometer. Quantitative measure-ments of crushed samples representing 2-inch long segments will be made using a Geli detector and 1024 channel analysis system. This study is being undertaken to better characterize the nature and extent of the residual radioactivity associated with past reactor operations and provide a basis for hazard evaluation related to release of the facility to unrestricted use.
No items of noncompliance were identified.
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' Exit' Interview The inspector met with licensee representatives at the close of the inspection. The licensee representative will keep Region V, ISE informed of the progress of this phase of the evaluation study and plans to prepare a summary report of results of the sample analysis.
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