IR 05000148/1980001
| ML20003C237 | |
| Person / Time | |
|---|---|
| Site: | 05000148 |
| Issue date: | 12/18/1980 |
| From: | Gagliardo J, Spangler R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20003C234 | List: |
| References | |
| 50-148-80-01, 50-148-80-1, NUDOCS 8102270291 | |
| Download: ML20003C237 (4) | |
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U. S. NUCLEAR REGULATORY. COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-148/80-01 Docket No. 50-148 License No. R-78 Licensee:
University of Kansas P. O. Box 2067 Lawrence, Kansas 66044 Facility Name:
University of Kansas, Bendix Pool Reactor Inspection at:
University of Kansas, Lawrence, Kansas
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Inspection (onducted:
December 3-4, 1980 l
/2.G!?o Inspector-H (. G. Spjngler, Reactor Inspector Date
)6!30 Approved byt It 7.\\ E. Gag} iardo, Chief, Nuclear Support Section Date Inspection Summary Inspection on October 22-24, 1979 (Report No. 50-148/80-01)
Areas Inspected:
Routine, unannounced inspection of organization, logs and records; review and audit; requalification training; surveillance; experiments; radiation control; follow-up on inspector identified problems; follow-up on items
I of noncompliance; procedures; environmental monitoring; and the emergency plan.
l This inspection involved 10 inspector-hours on-site by one NRC inspector.
Results: Within the eleven areas inspected, no violations were identified.
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1 DETAILS 1.
Persons Contacted B. Friesen, Radiation Safety Officer
- R. Mesler, Reactor Supervisor H. Woody, Reactor Operator
- Denotes presence during the exit interview.
2.
Inspector Follow-up of Previously Identified Items (Closed) Item of Noncompliance (Inspection Report No. 79-02, Paragraph 3):
Failure of the Nuclear Review Committee to Conduct a Design Change Review.
The licensee has completed all actions indicated in their response to this item.
3.
Organization, Logs and Records The inspector reviewed the facility operations log and the associated startup check list for the period November 9, 1979 to November 14, 1980 (last entry).
The annual report dated September 22, 1980, was also reviewed.
These logs and the annual report appeared to be' complete and to represent an accurate history of the facility's operation.
It also appeared that the Technical Specificstion requirements addressing the facility organization were being met.
Reactor startups were conducted for requalification training, absorber material irradiations and demon-strations.
No adverse findings were identified.
4.
Review and Audit The inspector examined the Nuclear Review (NR) Committee minutes for December 20, 1979, March 3, 1980, June 7, 1980 and September 23, 1980 and the facility annual audit conducted on June 5, 1980 and reviewed by the l
NR Committee on September 23, 1980.
The NR Committee met quarterly with I
a quorum present as required by the license.
Several minor problems were l
identified during the annual audit and were resolved by the NR Committee.
There were no further findings in this area.
l 5.
Surveillance
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The inspector verified that all license required surveillance activities
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were conducted at the required frequency and provided acceptable results.
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All Technical Specification design criteria, limiting condition for operation and limiting safety system settings appeared to have been met.
No violations were identified in this area.
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6.
Experiments The inspector reviewed the Irradiation Record and Order Forms for the period December 11, 1979 to September 16, 1980.
IrradMions were per-formed on cobalt and indium foils and an aqueous ab mrber solution in one case.
Each irradiation was reviewed, approved and conducted in accordance with the facility's experiment procedure.
No violations were identified in this portion of the inspection.
7.
Research Reactor Requalification Training The inspector determined that all currently licensed operators are satis-factorily participating in the requalification program The biannual written examination was administered by H. O. Woody on December 20, 1979.
Annual evaluations for all operators were documented in December of 1979 and the annual review of the emergency procedure was conducted during the December NR Committee meeting.
No further findings were identified.
8.
Procedures The license procedure requirements and facility procedures were reviewed by the inspector.
From this review the inspector determined that there appeared to be sufficient procedures to meet the license requirements and that they were adequate considering the level of use of this facility.
The inspector inoi::ated to the Reactor Supervisor that the Rod Drop Pro-cedure was somewhat lacking in detail and could be improved with the addition of a few more steps.
No violations were identified during this portion of the inspection.
9.
Radiation Control and Environmental Protection The inspector reviewed the facility's procedures, posting requirements, and radiation area markings and reviewed, on a sampling basis, the follow-ing records:
(a) Reactor Bay Ventilation Filter Change Log (b) Air Sample Data Sheets (c) Water Sample Data Sheets (d) Calibration Log (e) Area Survey (HP Form -9)
(f) Reactor Demineralizer Check Log
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All recorded levels of contamination, radiation levels and radiation dose rates appear to be within the 10 CFR 20 limits.
The sample data sheets were completed and the radiation instrument calibrations had been completed during this year.
No adverse findings were identified in this area.
10.
Emergency Plan The inspector reviewed the facility emergency plan and noted that a drill had been conducted by the Radiation Safety Officer on April 15, 1980.
The results of this drill were reviewed by the NR Committee during this May 7, 1980 meeting.
Although coordination with the campus police, the university hospital and local fire department had been established, these agencies did not participate in the April 15 drill.
The Radiation Safety Officer, during discussions with the inspector, indicated that he intends to include these agencies in the next scheduled emergency drill.
No further findings were identified in this area.
11.
Followup on IE Bulletins / Circulars The Reactor Supervisor received and reviewed IE Circular 80-02, Nuclear Power Plant Staff Hours, and Circular 80-14, Radiation Contamination of Plant Demineralized Water System and Resultant Internal Contamination of Personnel.
The design and operation of the facility is such that the subject matter of these circulars is not applicable.
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12.
Exit Interview An exit interview was held with the Reactor Supervisor at the conclusion of this inspection.
The findings noted above were identified by the inspectors and acknowledged by the Reactor Supervisor.
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