IR 05000243/1980002
| ML19323A415 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 03/06/1980 |
| From: | Carlson J, Morrill P, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19323A408 | List: |
| References | |
| 50-243-80-02, 50-243-80-2, NUDOCS 8004210196 | |
| Download: ML19323A415 (5) | |
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U. S. NUCLEAR REGUIATORY COMMISSION
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OFFICE OF INSPECTIO'; AND ENFORCEMENT
REGION V
Report No.
50-243/80-02 50-243 License no, R-106 Safeguards Group Docket No.
Licensee:
Oregon State University Corvallis, Oregon 97331 TRIGA (OSTR)
Facility Nace:
TRIGA Site, Corvallis, Oregon Inspection at:
February 26-27, 1980 Inspection conducted:
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Inspectors:
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P. Jl, Morrill, Regctor Inspector
. Date Signed P( %JXkt 3/s /2 o J.D;. Car.lson,ReActdhInspector
'Da:.c Signed Date Signed
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N Approved By:
o 6-D. M. Stev'perations and. Nuclear Support Branch nberg, Chief, Reactor Project Section 1 Date Signed Reactor O
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S u=na ry :
Inspection on February 26-27, 1980 (Report No. 50-243/80-02)
Areas Inspecte_d_:
Routine, unannounced inspection of organization, logs and records; review and audit; requalification training; refueling (partial);
surveillance; experiments; and miscellaneous independent inspection effort, including a tour of the facility and observation of selected aspects of fa-cility checkout and operation. This inspection involved 22 regular inspector hours by two NRC inspectors.
Results: Of the eight areas inspected, no items of noncompliance or devi-ations were identified.
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RV Form 219 (2)
8004210[ %
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DETAILS 1.
Persons Contacted Princioal Licensee Employees Dr. C. H. Wang, Reactor Administrator
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- Dr. J. C. Ringle, Chairman, Reactor Operations Comittee
- A. G. Johnson, Radiation Center Health Physicist
- T. V. Anderson, Reactor Supervisor The inspectors also talked with and interviewed several other licen-see employees.
- Denotes persons attending exit interview.
2.
Organization, Logs and Records i
Organization, logs, and records pertaining to plant operations since October 1978 were examined by the inspectors.
This examination inclu-ded discussions with facility personnel and a review of selected por-
tions of the following:
Annual Report, dated 31 August 1979 Daily Power Logs
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Control Poom Log Sheets Console Logs Startup Checklists Shutdown Checklists Reactor Supervisor's Log Red Calibration June 1979 Fower Cclibration January 1979 & June 1979
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Irradiation Requests
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Administrative Procedures Tne infomation in the Annual Report pertaining to reactor operations appeared consistent with that obtained during this inspection. There have been no significant changes in management of the facility since the last inspection.
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fio items of noncompliance or deviations were identified.
3.
Review and Audit
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The licensee's review and audit activities since flovember 1978 were examined by the inspector. This examination included discussions with
licensee management and a review of the following records:
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-2-Reactor Operations Committee (ROC) Charter ROC Audit Reports Minutes of ROC Meetings I
Experiment B-21
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The inspector verified the review and audit functions are being per-i formed in accordance with the requirements of the technical specifi-cations.
flo items of noncompliance or deviations were identified.
4.
Exoeriments
The inspector examined the irradiation requests and experiment proce-dures.
The inspector verified by review of records and discussion with facility personnel that the experiments were reviewed and approved by the Reactor Operations Committee as required.
One modification to ex-
periment B-21 was authorized during the past year in accordance with
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10 CFR 50.59, and as stated in the licensee's Annual Report. The re-activity effect was predicted beforehand and confirmed by measurement.
Limits on shutdown margin, excess reactivity, and individual / total worth of experiments were not exceeded, fio items of noncompliance or deviations were identified.
5.
Refueling Activities The inspector examined the procedure governing refueling activities and fuel movenent (0 STROP 11.0).
No refueling had occurred; however, during a core configuration charge to accomodate an experiment, fuel elements were moved to place the core in an asymetric configuration.
This resulted in a reportable occurence (dated June 19,1979)when the shutdown margin dropped below the technical specification limit.
The licensee reported the problem to NRC correctly and committed to change OSTROP 11.0 to provide additional guidance regarding cone ex-cess and shutdown margins during configuration changes.
The change to OSTROP 11.0 had not been made at the time of the inspection. The licensee comitted to changing the procedure prior to using OSTROP 11.0 for refueling or core configuration changes, fio items of nonconpliance or deviations were identified.
6.
Operator Requalification Program i
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-3-The 11censee's operator requalification program was reviewed against the requirements of 10 CFR 55 and the approved operator requalifica-tion program.
Records and discussions with licensee personnel showed the scheduling and conduct of lectures and examinations required by NRC Regulations have been satisfactory during the past year.
The inspector verified that the licensee was maintaining and using a log at the operator's console to keep licensed personnel aware of changes in procedures, facility design, and the facility license.
The inspector also verified the licensee's corrective actions regarding the documentation of operator operational competency.
No items of noncompliance or deviations were identified.
7.
Research Reactor Procedures This: inspection included an examination of the licensee's operating procedures for technical adequacy and for compliance with regulatory requirements.
Procedures reviewed were those associated with reactor startup and steady state operation, reactor shutdown, refueling, and conduct of experiments. A walk-through of selected procedure check lists verified that they would accomplish their intended purposes.
Change No. 4 to the Facility Operating license was issued on December
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18, 1979 to permit replacement and upgrading of electronics in the reactor console, increase operating limits for reactivity, reflect a title change of one of OSU's principal officers and extend the time period for submission of the annual report. The inspector observed that although the start-up and shut down check lists had been changed to reflect change No. 4 the " Reactor Start Up Check List Procedure" (OST REP 2.0) had not been changed. The inspector also observed that a copy of the technical specification in the control room had not been amended to reflect change no. 4.
The inspector verified that an op-erating bulletin had been issued by the Reactor Supervisor to make all operators aware of change no. 4.
License representatives stated that they would develop a list of spe-cific documents to be kept up to date. These would include copies of the operating license, technical specifications, reactor operating procedures (OSTROP's), emergency plan, and experiments.
These docu-ments would be brought up to date to reflect change no. 4 to the oper-ating licensee and to incorporate any other changes required by NRC regulatory requirements by June 30, 1980.
No items of noncompliance or deviations were identified.
8.
Surveillance An examination of surveillance activities was conducted during the inspectio,
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-4-The inspector's examination of procedures and observation of facili-ty operation showed that, for selected parameters without technical spec-ification surveillance requirements, facility operation was consistent with limiting conditions for operation in the technical specifications.
The inspector also examined licensee records to verify the accomplish-ment of other selected surveillance tests required by the technical specifications.
No items of noncompliance or deviations were identified.
9.
Independent Inspection
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The inspection included a tour of the facility, observation of daily startup checks for the training of student operators, pulse and power mode operation. The inspectors also examined the licensees replace-ment and upgrading of electronics is in the reactor console.
fio items of noncompliance or deviations were identified.
10.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)attheconclusionoftheinspectiononFebruary 27, 1980.
The in-spectors summarized the scope and findings of the inspection. Licen-see representatives made no commitments other than that discussed in Paragraph 7 of this report.
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