IR 05000106/1980003
| ML19338G268 | |
| Person / Time | |
|---|---|
| Site: | 05000106 |
| Issue date: | 09/23/1980 |
| From: | Book H, Curtis J, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19338G259 | List: |
| References | |
| 50-106-80-03, 50-106-80-3, NUDOCS 8010280706 | |
| Download: ML19338G268 (3) | |
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U. s. NUCLEAR REo0LAToRY Co.v.IssIoN
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OFFICE oF INsFEC~ ion AND ENFoRCEF.ENT
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R GIoN V
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Rsport No.
50-106/80-ON3
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Docket No.
50-106 License No.
D.C1 Safeguards Group
Licensee:
Oregon State University Nuclear Radiation Center Corvallis, Oregon 97331 Facility Name:
OSU AGN-201 Reactor
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Corvallis Inspection'at:
Inspection conducted: -September 9, 1980 f
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Inspectors:,
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,pd.R. Cur:1s, Raciation Specialist Date-s'igned Date signed
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Approved By.:
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F. Wens awski, C 'ef, Reactor Radiation Safety Section D'8t*'Si U*d S
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Approved By:
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H. E. Book, Chief, Fuel Facility and Materials Safety Branch na'te signed surnnary :
A special close-out inspection was conducted to observe the condition of the facility and verify that the licensee conducted surveys and documented results as they were described in the Final Decommissioning Report, 0.S.U. AGN-201 Reactor dated July 9,1980 and submitted to NRR, USNRC, Attn: R. W. Reid, Operating Projects Branch 4 on July 10, 1980.
The insoector toured the facility, conducted meter and smear surveys of the facility and its immediate surroundings, examined licensee records, and interviewed persons who were involved in the prior use, dismantling and preparation of the facility for release for unrestricted use.
The insp?ction invcived four hours onsite by one inspector.
Results:
Based on the findings of this inspection including results of surveys
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i 9,1980, cited above.
RV For:r 719 (7)
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l 8010280706
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DETAfLS
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Persons Contacted
- C, H. ' Wang, Director, OSU Huclear Radiaticn Center J. C. Ringle Assistant Reactor Administrator
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- A. G. Johnson, Senicr Health Physicist
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The Facility The room that housed the AGN-201 is approximately 35 feet long and 30
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-The AGN-201 reactor was moved into its present location in the Radiation Center on 15 July ~1964. The last date of reactor operation was~12 Dec'imbeF" 1974 The control rods were removed and the reactor was placed in long
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term shutdown '(LTS) on 28 May 1975.
It has remained in the LTS condition
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since_that date. _ Application was made to decommission the reactor on '
8 March 1979.
Schedules and the necessary approvals for dismantling were submitted and granted and the AGN 201 dismantling was conducted between June 10 and_20, 1980. The monitoring of the dismantling operations _and the survey of the radiological. conditions of the space after removal
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of the reactor were described in the licensee's report dated July 9,.
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1980;_ titled, Final Decommissionino Report, Oregon State University
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AGN-201 Reactor.
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-3.2 Radiation SurveyY
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The inspector toured the facility with the licensee's senior health physics
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representative who had participated in the dismantling project, discussed survey techniques and results, examined survey and personnel monitoring
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.The. inspector's radiation level survey consisted of measuremenMof the gama radiation levels at approximately three feet above the floor throughout the facility and within six inches of the ficar in specific areas in
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the imediate area where the AGN-201 reactor was located..No radiation
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levels above the.nor=al background of 5 to 15 micro r~ per. hour ~ were~identifiec.
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.. <The contamination survey consisted of thg measurement of removable contamination by taking smears of approximately 100 cm area with dry filter paper discs
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at selected locations in the facility, and the measurement of beta-gama count rates with a thin window, pancake type GM tube detector over selected
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floor-surfaces.at a distance of one-half to one inch above the surface.g.
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The smear samples w;re counted in an MRC laboratory-type windowless, gas
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flow pr~ portional counter and the counMng results from all smears were
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at or below the background count rate of 30 ccants per minute. The meter
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suriey of floor surfaces with the pancake GM tube probe indicated no readings
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l above the normal background of 30 to 50 counts per minute.
The instrumentation used by the licensee in their surveys was:
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Technical Associates PUG-1, Serial No. 3020 with p-11 thin-window G. M. pancake tube probe.
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Technical Associates Cp7, Serial No.12528 Cutie pie Ion chamber
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type survey meter.
These instruments were calibrated June 11, 1980.
The instrumentation used by the inspector in the September 9,1980 survey was:
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Eberline Model E520 Serial No.18SS with HP 260, thin window GM pancake probe.
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Eberline PRM-7, Micro R Meter Serial No. 247 with NaI Scintillation crystal detector probe.
These instruments were calibrated in August 1980 and February 1980 respectively and were response checked in the week prior to the inspection, September 2-5, 1980.
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The survey record; examined and the discussions with the licensee staff
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who participated in the dismantling operation disclosed.that with the exception of the expected radiation levels detected en the fueled core can and control rods (0.5 to 10 mrem /hr), no radiation levels or radio-activity above nor al background levels were detected on reactor' components, associated electronic and laboratory equipment or on floor surfaces in.
the facility.
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The fueled core and control rods were removed and transported to the TRIGA Facility for secured storage. The other reactor ccmponents were thoroughly.conitored and surveyed, cleared and transferred:to a university storage facility.
These conditions were confirmed by the -inspector during
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the tour and independent survey performed on September 9,1980.
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Exit Interview.
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An exit. interview was held at the close of the inspection. 3-In. addition:-- :-
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to the individuals ' designated in paragraph (1), W. Dixon," Oregon State
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Department of Energy representative was also present. The inspector reviewed the scope and findings of the inspection and indicated that
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based on the: surveys performed and on the conditions observed,his report-i would confirm that the AGN-201 Reactor had been dismantled as described in the licensee's dismantling report and the conditions found at the j
. facility met the guidelines of Reculatory Guide 1.86, Termination of Operatino Licenses for Nuclear Reactors, j
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