IR 05000252/1990001
| ML20043E203 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 06/04/1990 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20043E200 | List: |
| References | |
| 50-252-90-01, 50-252-90-1, NUDOCS 9006120154 | |
| Download: ML20043E203 (8) | |
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APPENDIX
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V,S. NUCLEAR REGULATORY COMMISSION
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REGION IV
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NRC Inspection Report: _50-252/90-01 Operating License:
R-102
Docket:- 50-252
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Licensee: University of New Mexico (UNM)
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~ Chemical & Nuclear Engineering
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Department
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209 Farris Engineering Center
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l Albuquerque, New Mexico 87131
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(4 Facility Name: AGN-201/M Reactor (5 Watts)
. Inspection At:.UNM, Albuquerque, New Mexico
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Inspection Conducted: May 7-10, 1990 Inspector:
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D R<' E Baer, Radiation Specialist, Facilities Date Radiological Protection Section
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B, VLrray, Chief, Facilitio ~ Radiological Da'te Protection Section
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Inspection Summary
. Inspection Conducted May 7-10, 1990 (Report 50-252/90-01)
2 Areas Inspected:
Routine, unannounced inspection of the. licensee's reactor operations, emergency _ preparedness, radiological protection, material accountability, and physical security plan.
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Results: The_ licensee's program for reactor operations, emergency
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preparedness, radiological protection, material. accountability, and physical
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security for-the AGN-201M reactor facility appears to be effectively-
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Within the areas inspected, there was one licensee-identified violation involving the. committee on radiological control meeting (see paragraph 14). No deviations were identified. One previously identified inspection finding was-closed (see paragraph 2).
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DETAILS-1.
Persons Contacted
- R. D. Busch, Chief Reactor Supervisor L. L. Cleveland, Radiation Safety Technologist III
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R. B. Counsellor, Radiation Safety Officer, UNM Li A.-L. Roybal, Captain,-UNM Police Department
- Denotes those present during the exit-interview on May 10, 1990.
2.
Followup on previously Idertified Items l
(Closed) Violation 252/8801-01:
Failure to Submit Annual Operating Report - This item was previously discussed in NRC Inspection Report 50-252/88-01 and involved the failure to submit the required annual operating report.
The licensee submitted an annual operating report for the period July 1, 1986, through June 30,.1987, to NRC on March 28, 1988.
3.
Observations The following are observations the inspector discussed with the licensee during the exit interview on May 10, 1990.
These observations are not violations,-deviations, unresolved-items, or open items.
These observations were identified for licensee consideration for program improvement, but the observations have no specific regulatory requirement.
Letters of agreement for. fire and ambulance service (see paragraph 18).
- Site-specific training for fire department personnel (see paragraph 18).
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4.
Organization and Management Control The licensee's organization and management control was inspected to determine compliance with Technical Specification (TS) 6.1.
The' current organization and assignment of responsibilities was verified to be consistent with TS requirements. The inspector reviewed the status of licensed operators, membership and meetings of the reactor operations committee and reactor safeguards advisory committee (RSAC), and other matters concerning supervision of the reactor facility, The inspector verified that the chief reactor supervisor and licensed
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reactor operators met or exceeded the minimum qualifications as set forth s.
in ANSI /ANS-15.4-1988, " Standards for Selection and Training of Personnel for Research Reactors."
No violations or deviations were identifie ]
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Operation and Maintenance Logs The inspector reviewed the reactor operation log, reactor maintenance log, and surveillance records for the period March 3,1988, through May 10, j
1990, to determine compliance with the requirements of TS 2.0, 3.0, 4.0, and 6.10.
The inspector reviewed the licensee's activities regarding maintenance, modifications, upgrades, startup checklist, experiment records, reactor power levels, and personnel exposure and dosimetry logs.
Maintenance records were also reviewed for 10 CFR 50.59 evaluations and RSAC reviews of reactor modifications, upgrades, and component replacement.
The inspector noted that the licensee documented some surveillance and maintenance activities in the monthly inspection record and the annual
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maintenance activities in the reactor maintenance log.
The maintenance
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log was not considered to be a detailed record for all maintenance activities.
All maintenance and operation activities appeared to have been conducted in a manner consistent with the TS requiremer.ts and administrative procedures.
'No viulations or deviations were identified.
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Internal Audits and Reviews
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The inspector rev,1ewed the minutes of the meetings conducted by the RSAC and verified that the committee had met semiannually since the previous inspection and reviewed all matters relating to the operation and maintenance of the reactor.
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The RSAC routinely reviews the facility's records for maintenance, operation, and inspection, the emergency plan, security plan, and their
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respective implementing procedures to verify conformance with the TS.
No violations or deviations were identified.
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Reactor Operations The reactor is used primarily for performing experiments associated with the nuclear engineering teaching program.
These experiments involve sample irradiation, approach to critical, reactivity measurements, period measurements, neutron temperature measurements, power calibration, flux distribution, and vuid coefficient measurements. The reactor is aise operated during demonstration courses and the operator requalification program.-
The reactor was last operated on April 19, 1990, and is not routinely
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operated during the summer months except for surveillance activities or operator requalification program requirements.
No violations or deviations were identified.
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Operator Requalification Training
The licensee's reactor operator requalification training program was reviewed to determine compliance with TS 6.3 and the operator requalification program, dated April 27, 1987.
The operator
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requalification program is designed to meet the conditions as set forth in 10 CFR Part 50.54(i) and 10 CFR Part 55, Appendix A.
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The inspector reviewed the individual licensed operator files and concluded that the operator requalification program was being implemented
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properly.
The inspector noted that of the four licensed senior reactor
operators (SR0s) for the UNM AGN-201M reactor, two SR0s had been on inactive status. One of the SR0s returned to an active status in February 1990.
No violations or deviations were identified.
9.
Procedures The inspector reviewed the licensee's written procedures to determine compliance with the requirements of TS 6.6.
The procedures associated with the reactor are contained in the manual,
"AGN-201M Reactor Operation and Operator Training Manual," dated July 1984. The licensee had not made any revisions to the established
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procedures since the last inspection.
No violations or deviations were identified.
10.
Surveillance Requirements The inspector reviewed the surveillance activities for safety channel calibrations, reactivity limits, control and safety systems, radiation monitoring systems, and reactor structure to determine compliance with TS 3.0 and 4.0.
The inspector verified that limits regarding excess reactivity, control and safety rod worth, scram capabilities, and-safety systems were not exceeded. Also, the required calibrations of radiation monitors and associated reactor instrumentation had been performed at the required frequency. The resiew of the surveillance and calibration test records did not indicate any unusual conditions.
No violations or deviations were identified.
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11.
Experiments
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The inspector reviewed the licensee's experiment records and reactor operation logs to determine compliance with the requirements of TSs 3.3, i
6.6, and 6.7.
The inspector determined the licensee had introduced one new experiment, void coefficient measurement, in the reactor since the previous inspection.
The new experiment had been approved by the RSAC prior to performance in the reactor. All experiments which had been conducted were used with approved procedures under approved reactor conditions.
No violations or deviations were identified.
12.
Fuel Handling Activities l
The inspector reviewed the licensee's fuel handling activities to determine compliance with the requirements of TS 5.2 and 6.10.2.c.
The inspector verified the licensee had approved procedures for fuel handling activities. The licensee had not made any changes to these procedures since the previous inspection.
The inspector determined by record review and discussions with personnel that fuel handling operations and startup tests had been carried out in conformance with the licensee's approved procedures.
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No violations or deviations were identified.
13.
Changes The inspector determined from discussions with licensee representatives and review of reactor maintenance and operation records that no changes had been made since the previous inspection to the facility or procedures that would require a safety evaluation pursuant to 10 CFR 50.59.
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The licensee had an inquiry from the Department of Energy relating to the cost to upgrade the reactor operator's console and replace the older vacuum tube instruments with state-of-the-art solid state instrumentation and other associated reactor components.
There has been no decision as to when these changes might be made.
No violations or deviations were identified.
14.
Radiation Protection The inspector reviewed the licensee's radiation protection program to determine compliance with the requirements of 10 CFR Parts 19 and 20; and TSs 3.4, 4.4, 6.10.1.e, and 6.10.2.d.
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The inspector reviewed selected records and logs, interviewed personnel, made observations, and performed independent radiological surveys adjacent to the facility.
TS 6.1.4 requires that meetings for the committee on radiological control be held at least quarterly (interval not to exceed 4 months).
The licensee had determined on April 11, 1990, that the quarterly meetings
for the second quarter of 1988 and 1989 had not been held as required.
This error was attributed to a breakdown in communications and members of the committee were not fully aware of this requirement in Amendment 3 for Facility Operating License R-102, issued on March 24, 1987. The licensee has scheduled a meeting of the committee for the second quarter of 1990.
The licensee's corrective action was reviewed by the inspector on May 9, 1990, and determined it to be adequate to correct the self-identified violation and prevent recurrence.
This matter would normally be considered a violation of TS 6.1.4 requirements. However, the NRC Enforcement Policy, 10 CFR Part 2, Appendix C (1989), states that a Notice of Violation will generally not be issued for violations identified by the licensee, if:
(1) it was identified by the licensee; (2) it fits a Severity Level IV or V; (3) it was reported, if required; (4) it was or will be corrected; and (5) it was not a violation that could reasonably be expected to have been prevented by the licensee's corrective actions for a previous. violation. This violation meets the criteria specified in 10 CFR Part 2 Appendix C (1989), and is considered a licensee-identified violation and no Notice of Violation will be issued concerning this matter.
No deviations were identified.
15.
Environmental Surveillance / Radioactive Releases I
The licensee does not maintain a detailed environmental surveillance program (e.g., collection and analysis of water, soil, or vegetation samples). There is no specific license requirement that such a program be maintained.
A licensee representative stated that no liquid effluents have been made or discharged since the last inspection.
The licensee's operation records
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indicate that gaseous releases are within 10 CFR Part 20 limits.
No violations or deviations were identified.
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16. Transportation (Fuel Shipments)
The inspector verified that there had been no fuel shipments since the previous operational inspection.
No violations or deviations were identified.
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l 17. Nuclear Materials Safeguard The inspector reviewed the nuclear material inventory program to determine
compliance with License Condition 2.B (2).
The inspector reviewed the accountability procedures, practices, and material status records. The procedures, practices, and records were
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found to be well implemented.
Responsibilities and response requirements were defined clearly and understood, and sppropriate test procedures were being used. The licensee had not received or shipped any materials since the previous inspection.
No violations or deviations were identified.
18.
Emergency planning The inspector reviewed the emergency preparedness program to determine
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compliance with the emergency plan, dated October 25, 1989, and approved by the NRC on March 21, 1990.
The inspector reviewed the letters of agreement with the city of Albuquerque for fire department services, dated February 6, 1985,
Albuquerque Ambulance Services, dated February 26, 1985, and the UNM Hospital, dated October 9, 1989, for medical services.
The inspector discussed with licensee representatives the need for the letters of agreement with the fire and ambulance service to be reconfirmed. The r
licensee acknowledged that these letters would be reconfirmed.
The inspector also discussed training. The university does not provide training for fire and ambulance service personnel. The licensee stated that this training is provided by a local department of energy cuntractor.
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The inspector discussed the advantage of providing additional
site-specific training for at least the first response station personnel of the fire department. The licensee stated that they would review this training. The UNM Hospital is well equipped and trained to provide for a radiological medical emergency.
The school of medicine personnel have written books on the topic of medical management of radiation accidents
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and have provided training for other medical personnel.
The inspector reviewed the results of the annual emergency drills and associated evaluations made by the licensee.- The inspector noted that during the June 1988 drill, radiation safety personnel did not arrive until 35 minutes after the emergency was declared.
Radiation safety personnel did not have transportation available and called the university police who responded but en route to the reactor facility the police officer stopped to issue a traffic violation.
The inspector discussed with licensee representatives the response by university police. The licensee stated that officers have been instructed on the setting of priorities when en route to an emergency, drill or actual event.
No violations or deviations were identifie.
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s 19. Physical Security The inspector. reviewed the implementation of the licensee's physical security plan to determine compliance with 10 CFR Part 73.
A No violations or deviations were identified.
20. Exit Interview The inspector met' with licensee representatives identified in paragraph 1.
at the conclusion of the inspection on May 10, 1990, The inspector
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. summarized the scope and findings of the inspection.
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