IR 05000252/1979002
| ML19294B248 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 11/28/1979 |
| From: | Madsen G, Spangler R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19294B243 | List: |
| References | |
| 50-252-79-02, 50-252-79-2, NUDOCS 8002280046 | |
| Download: ML19294B248 (5) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENY
REGION IV
Report No.
50-252/79-02 Docket No.
50-252 License No. R-102 Licensee:
University of New Mexico (UNM)
Albuquerque, New Mexico Facility Name: AGN-20lM Reactor (5 Watts)
Inspection Conducted: November 19-21, 1979 bd?h /9 O Ph/
Inspector:
11. G. Spangler, Reactor Inspector Date Approved By:
N [ac b W
// h P h 4 Ti. L. Madsen, Chief, Reactor Operations and Date fluclear Support Branch Inspection Summary Inspection on November 19-21, 1979 (Report No. 50-252/79-02)
Areas Inspected:
Routine, Unannounced inspection of the licensee's organization, operations and maintenance logs, licensee's internal review and audit program, requalification program, operating procedures, surveillance requirements, experiment review radiation protection, environmental protection, and emergency planning programs. The inspection involved 18.5 inspection-hours on-site by one flRC inspector.
Results:
No items of noncompliance or deviations were identified.
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-2-DETAILS 1.
Persons Contacted
- Dr. G. A. Whan, Reactor Administrator
- Dr. R. A. Knief. Chief Reactor Supervisor C. W. Woodstock, Reactor Operator W. Tabor, UNM Radiological Safety Officer
- Denotes those present during the exit interview.
2.
Inspector Followup on Previously Identified Items (Closed) Item of Noncompliance (Inspection Report 77-02, paragraph 7):
failure to give annual requalification written examinations in 1976.
The inspector verified that all 5 absequent written requalification exam-inations were given as required.
A scheduling board is being prepared which will implement sufficient administrative controls to prevent a recurrence.
3.
Organization The inspector reviewed the operational and administrative organization regarding the reactor to determine compliance with Technical Specification requirements.
Such items as status of licensed operators, membership and meetings of the Reactor Operation Committee and Reactor Safeguards Advisory Committee, and supervision of the reactor facility were examined.
flo items of noncompliance or deviations were noted.
4.
Operations and Maintenance Logs The inspectnr reviewed the following logs for the period July 1977 to November 1979 to determine that operations and maintenance activities had been properly conducted:
Reactor Operations Log Reactor Maintenance Log Monthly Reactor Inspection Log All maintenance and operations activities appear to have been conducted in a manner consistent with the Technical Specifications and administrative procedures.
The inspector selected the modification of the channel 2 nuclear instrumentation for a detailed analysis. The installation and calibration of the replacement instrumentation was documented on Reactor Maintenance Log Sheet, dated July 28, 1979, a' ' was reviewed prior to reactor startup by the UNM Reactor Safeguards
,m.. :sor Committee on August 29, 1979.
Temporary procedure revisions were made and the licensee
-3-is in the process of permanently updating drawings and the Manual of Operation for the AGN-201 reactor.
tio items of noncompliance or deviations were identified.
5.
Internal Audit and Review The records of audits and reviews performed by the licensee were examined.
The inspector verified that both the Reactor Safeguards Advisory Committee (SAC) and the Reactor Operation Committee (ROC) had met semiannually since the previous inspection to review matters related to operating the reactor.
The following items were routinely reviewed by the committees:
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Technical Specification Requirements
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Organization
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f!ew experiments
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Maintenance and Operations Logs
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Procedure Changes
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50.59 changes
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Radiation Surveys
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Equipment Performance No items of noncompliance or deviations were noted.
6.
Requalification Training The inspector reviewed the training documents for the currently licensed individuals and detemined that they had completed all required portions of the requalification program for 1977, 1978 and 1979 as follows:
Semiannual Annual Reactor Name
, 9'aining Session Written Exam Manipulations G. A. Whan 11/3/77 3/24/77 Satisfactory
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2/22 & 3/7/78 3/31/78
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10/19/78 8/25/79
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R. A. Knief 11/3/77 3/22/77
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2/22 & 3/7/78 3/31/78
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10/19/78 8/30/79
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C. W. Woodstock 11/3/77 3/24/77
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2/22 & 3/7/78 3/31/78
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10/19/78 8/28/79 The reactor was not operated from December 18, 1978 until September 6, 1979 because of a failed channel 2 power level instrument. Thus the semiannual retraining session for the first half of 1979 was not required to be conducted. The NRC was notified as required by 10 CFR 55.31.e and reaffimed operator certification based on the results of the 1979 written examinations by letter dated September 6, 1979.
No adverse findings were identified.
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-4-7.
Procedures The inspector reviewed operating procedures to determine compliance with Technical Specification requirements. fiost of the procedures associated with the reactor are found in the manual titled: Manual of_ Operation for the AGN-20lM Reactor, dated October 1971.
The manual contains procedures covering such items as:
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Administrative Organization
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General Reactor Operating Procedures Request for Reactor Use
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Reactor Operating Procedures
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Maintenance and Inspection Procedures
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Emergency Procedures Radiation protection procedures related to the reactor are also found in the University Radiation Safety Manual.
fio items of noncompliance or deviations were noted.
However, during the review of the Manual of Operation, the inspector did not find an admin-istrative method for identifying approved procedures and experiemnts and for controlling temporary and permment changes to these procedures and experiments.
This item was discussed with the licensee representatives who indicated that some thought was being given to revising the Manual of Operations; therefore, the inspector identified this as an open item for review in a future inspection.
fio further items in this area were identified.
8.
Surveillance, Reactor Core, Control and Instrumentation Systems The inspector reviewed Technical Specification requirements for surveil-lance of reactor core, control and instrumentation systems. The inspector verified that limits regarding excess reactivity, control and safety rods worths, core tank, scram and safety systems were not exceeded.
It was noted that surveillance tests were performed as specified in Technical Specification 4.0.
The records of surveillance test results did not indicate any unusual conditions.
flo items of noncompliance or deviations were noted.
9.
Experiments Item 3.0 of the Technical Specifications contain requirements for eval-uation and approval of experiments. The licensee's records indicated that no new experiments have been placed in the reactor since the previous inspection.
It was noted that all experiments placed in the reactor between July 1977 and flovember 1979 were properly approved experiments.
The inspector noted that the Manual of Operation does not clearly define the tenns " standard" and " nonstandard" experiment and
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-5-does not provide significant guidance as to the generic types of experiments that may be run without prior approval of the Reactor Safeguards Advisory Committee and the Reactor Operations Committee.
This item will be part of the open item review noted in paragraph 7 above.
No further findings were identified.
10.
Radiological Ccntrol The inspector reviewed the licensee radiation control program to determine compliance with the following requirements:
10 CFR 19.11 10 CFR 20.104.b 10 CFR 20.403 10 CFR 19.12 10 CFR 20.203.b 10 CFR 20.405 10 CFR 19.13 10 CFR 20.203.c 10 CFR 20.409 10 CFR 20.101.a 10 CFR 20.203.d 10 CFR 20.201.b 10 CFR 20.101.b 10 CFR 20.203.e 10 CFR 20.401.b 10 CFR 20.102 10 CFR 20.205 10 CFR 20.202 10 CFR 20.103.a 10 CFR 20.207 10 CFR 20.104.a 10 CFR 20.401.a No ' items of noncompliance or deviations were noted.
11.
Emergency Planning Emergency procedures are contained in Section V of the Operations Manual.
It was noted that an up-to-date emergency call list was posted on the facility bulletin board. The licensee's records indicated that several
- drills and meetings with campus security have been conducted since the previous inspection.
No items of noncompliance or deviations were noted.
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12.
Environmental Protection The licensee does not maintain a detailed environmental surveillance program (e.g., collection and analysis of water, soil, vegetation samples).
There are no specific license requirements that such a program be main tai ned.
A licensee representative stated that no liquid effluent releases have been made since the last inspection. The licensee's operation records indicate that gaseous releases are within 10 CFR 20 limits.
13.
Exit Interview An exit interview was held with representatives of the licensee on November 21, 1979 at the conclusion er this inspection. The findings not'< cn the previous paragraphs vere discussed with and acknowledged by the r t ep?.?sentatives.