IR 05000394/1979002
| ML19263E910 | |
| Person / Time | |
|---|---|
| Site: | 05000394 |
| Issue date: | 05/04/1979 |
| From: | Faulkenberry B, Johnson G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19263E907 | List: |
| References | |
| 50-394-79-02, 50-394-79-2, NUDOCS 7906250449 | |
| Download: ML19263E910 (1) | |
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U. S. NUCLEAR RECULAToRY COMMISSION OFFICE oF INSPECTION AND ENFORCEMENT
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REGloN V Report No.
50-394/79-02 Docket No.
50-394 License No.
R-12'i Safeguards croup Licensee:
California Polytechnic State University San Luis Obispo, California 93407 Facility Name:
Research Reactor (AGN-201)
Inspection at:
California Polytechnic State University Inspection conducted:
/ April 12y13,fl979 Inspectors:
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P. W. J6hnstpff, Reactor Inspector Da(e' signed
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Date Signed Date Signed Approved By:
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'2 s (M/79 e
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ate S Qned B. H. Faulkenberry, ClyieCReactor Project Section 2, Reactor Operations and Nuclear Support Branch Sutrma ry :
Inspection on Apr;l 12-13,1979 (Report No. 50-394/79-02)
Areas Inspected: Routine unannounced inspection of facility operations; organization and administration; surveillance; procedures; reactor operations; and a discussion of proposals to dismantle and decommission the facility.
The inspection involved nine inspector-hours onsite by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
RV Form 719 (2)
7906250L/N
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DETAILS
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1.
Persons Contacted
- R. W. Adamson, Reactor Administrator A. Z. Rosen, Campus Radiation Safety Officer
- Denotes those present at exit interview.
2.
Operations General The California Polytechnic State University Research Reactor is an AGN-201 type training reactor with.a maximum licensed power of 0.1 watt. The facil-ity has been in a long term shutdown since May of 1978. This condition of the facility is due to the only licensed operator, Dr. R. N. Christenen, having left the school for a position at the Ohio State University. The control rods have been removed and are stored in a secure locker.
(See Paragraph 3, below. )
The licensee has proposed that the facility be decortmissioned and has discussed this proposal with NRR. The licensee representative indicated that NRR has advised him as to what the requirements are and has sent to hin documents pertaining to the dismantling and decomnissioning of an AGN-201 facility.
No items of noncompliance or deviations were identified.
3.
Oraanization and Administration The facility organization has had two changes in personnel responsible for the safe operation of the reactor facility.
Drs.
P,. N. Christensen and L. Hall have both left the University, and have left two vacancies on the Reactor Safety Committee. A quorum of three members can still be raised for meetings to satisfy technical specification requirements.
The meeting minutes of the Reactor Safety Committee indicate that the conmittee had met at the required frequency and had revised reactor operations pursuant to technical specification requirements.
No items of noncompliance or deviations were identified.
4.
Reactor Operations No operations of the reactor occurred during the past year as indicated by the following records and discussions with licensee representatives:
Supervisor's Log Reactor Operation Log Maintenance Log Surveillance Log Sheets Startup and Shutdown Log Sheets No items of noncompliance or deviations were identified.
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5.
Surveillance With the facility in long term chuidown, the technical specification requirements for surveillance of the t aactor are not required to be done until a subsequent startup. There is
..s intention by the licensee to startup the facility again; therefore, there is no likelihood of any surveillance being done between this inspection and the final disposi-tion of the reactor. The licensee is continuing radiological surveys and security checks of the facility and will continue to do so until the reactor is deconmissioned.
No items of noncompliance or deviations were identified.
6.
Procedures The operating and emergency procedures in use at the facility were examined by the inspector and discussed with the licensee representa-tive. The inspector confirmed that the procedures were consistent with the requirements of Section VI.B of the facility technical specifications.
No items of noncompliance or deviations were identified.
7.
Exit Interview The inspector met with the licensee representative (denoted in Paragraph 1)
on April 13, 1979. The inspector sunnarized the purpose and scope of the inspection and the findings. The licensee representative was apprised by the inspector of his license cormitments during the period the facility will be in long term shutdown. The licensee representative indicated that any changes to the facility status would be reported to the NRC Region V office, this pertains to the facility's decommissioning (see Paragraph 2).
The licensee represer;tative made no further statements or commitments other than the above.
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