ML20153C451
| ML20153C451 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 05/03/1988 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20153C429 | List: |
| References | |
| 50-252-88-01, 50-252-88-1, NUDOCS 8805060233 | |
| Download: ML20153C451 (8) | |
See also: IR 05000252/1988001
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APPENDIX B
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U.S. NUCLEAR REGULATORY COMMISSION-
REGION IV
NRC Inspection Report:
50-252/88-01
License:
R-102
Docket:
50-252
Licensee:
University of New Mexico (UNM)-
Albuquerque, New Mexico 87131
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Facility Name:
AGN-201/M Reactor (5 Watts)
Inspection At:
UNM, Albuquerque, New Mexico
Inspection Conducted:
March 28-31, 1988
Inspector:
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R.'E. Baer, Senior Radiation Specialist
Date
Facilities Radiological Protection Section
Approved:
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B. Murray, Chief,
Rytiiological Protection
Ddte /
and Safeguards Br&nch
Inspection Summary
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Inspection Conducted March 28-31, 1988 (Report 50-252/88-01)
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Areas Inspected:
Routine, unannounced inspection of the licensee's
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organization, operations and maintenance logs, licensee's internal review and
audit program, requalification program, operating procedures, surveillance
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requirements, experiments, radiation protection, environmental protection,
emergency planning, and physical security plan.
Results:
Within the areas inspected, one violation was identified (failure to
submit an annual report, paragraph 13).
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DETAILS
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1.
Persons Contacted
F. L. Williams, Chairman, Chemical and Nuclear Engineering Department
- R. D. Busch, Reactor Supervisor
- K. Carpenter, Senior Electronics Technician
R. Counsellor, Radiation Safety Manager
R. T. Raymond, Lieutenant, UNM Police Department
- Denotes those present during the exit interview on March 31, 1988.
2.
Followup on Previously Identified Items
(Closed) Violation (252/8601-01):
Failure to implement operator
requalification program - This item was identified in NRC Inspection
Report 50-252/86-01 and involved the lack of operational recertification
and annual written examinations.
The licensee had implemented the
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operator and senior operator requalification program as submitted and
approved on April 12, 1987.
(Closed) Violation (252/8601-02):
Failure to perform adequate surveys -
This item was identified in NRC Inspection Report 50-252/86-01 and
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involved the lack of area radiation surveys with properly calibrated
radiation survey meters.
The licensee had implemented a calibration
program for radiation survey and measurement instrumentation.
All
radiation surveys were being performed with properly calibrated
instrumentation.
(Closed) Violation (252/8601-03):
Physical security plan - This item was-
identified in NRC Inspection Report 50-252/S6-01 and involved
implementation of the physical security plan.
The licensee had fully
implemented the physical security plan.
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(Closed) Unresolved Item (252/8601-05):
Radiation protection training -
This item was identified in NRC Inspection Report 50-252/86-01 and
involved the training provided to all personnel to satisfy the
requirements of Regulatory Guide 8.13, "Instruction Concerning Prenatal
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Radiation Exposure." The licensee includes training on Regulatory
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Guide 8.13 in "CHNE-431 - Nuclear Engineering Laboratory" and
"Introduction to Radiation Safety."
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3.
Inspector Observations
The following are observations the NRC inspector discussed with the
licensee during the inspection and at the exit interview on March 31,
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1988.
These observations are neither violations nor unresolved items.
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These items were recommended for licensee consideration for program
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improvement, but they have no specific regulatory requirement.
The
licensee stated that these observations would be evaluated for program
improvement.
Operating Procedures appeared weak'in addressing irradiations,
experiments, and maintenance that~could affect the safety of the reactor.
(paragraph 9)
Reactor Operation and Operator Trainin'g Manual did.not contain the current
technical specifications for the reactor facility.
(paragraph 9)
Annual Radiation Survey is not a comprehensive survey of the reactor room.
(paragraph 15)
4.
Organization and Management Control
.The NRC inspector reviewed the organization and management controls to
determine compliance with Technical Specification (TS) 6.1.
The current organization was verified to be consistent with Section II,
"Administration," of the AG-201M Reactor Operations and Operator Training
Manual, dated July 1984.
The NRC 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 licensee had
increased the membership of the RSAC from four to five members.
The NRC
inspector noted RSAC membership listed in the June 1, 1986, through
June 30, 1987, annual report listed only four members.
No violations or deviations were identified.
5.
Operation and Maintenance Logs
The NRC inspector reviewed the following logs for the period May 1986
through March 1988 to determine compliance with TS 2.0, 3.0, 4.0, and
6.10.
Reactor Operations Log
Reactor Maintenance Log
Monthly Reactor Inspection Log
All maintenance and operation activities appeared to have been conducted
in a manner consistent with the TS requirements and administrative
procedures.
No violations or deviations were identified.
6.
Internal Audits and Reviews
The NRC inspector reviewed the minutes of meetings conducted by the RSAC
and verified the committee had met semiannually since the previous
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inspection and reviewed matters relating to operating the reactor.
It was
verified that records reflected attendance by designated committee
members.
The following items were routinely reviewed by the committee:
TS Requirements
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Maintenance, Operations, and Inspection Logs
Security Plan
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Equipment Performance
Procedure Changes
Radiation Surveys
The NRC inspector discussed with licensee representatives the planned
audit of the security plan. - The licensee stated this audit would be
conducted by members of the RSAC and submitted for approval at the next
RSAC meeting.
The RSAC will also review inspection reports to identify
areas of concern, violations of regulatory requirements, and corrective
actions.
No violations or deviations were identified.
7.
Reac, tor Operation
The reactor is used primarily for performing experiments associated with
the nuclear engineering teaching program.
These experiments involve
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sample irradiation, approach to critical, reactivity measurements, period
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measurements, neutron temperature measurements, power calibration, and
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flux distribution.
The reactor is also operated during demonstration
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courses and the operator requalification orogram.
On March 30, 1988, the NRC inspector witnessed startup, operation, and
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shutdown of the reactor during performance of a standard operator
requalification program demonstration.
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No violations or deviations were identified.
8.
Requalification Training
The licensee's NRC approved Reactor Operator and Senior _ Operator
Requalification Program dated April 12, 1987, was reviewed.
The program
is designed to meet the conditions as set forth in 10 CFR Part 50.54(i)
and 10 CFR Part 55, Appendix A.
The NRC inspector reviewed the individual licensed operators files and
concluded that the operator requalification program as described and
approved is being implemented.
No violations or deviations were identified.
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9.
Procedures
The NRC 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 manual contains
procedures for the following categories:
General Design Features.
Administration
Operating Procedures
Maintenance and Inspections
Technical Specifications
The NRC inspector noted that the operating procedures appeared weak in the
area of conduct of irradiations and experiments that could effect the
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operation or safety of the reactor and preventative or corrective
maintenance which could affect the safety of the reactor.
The NRC
inspector also noted that the TS contained in the manual did not contain
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all the information included in the current TS.
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No violations or deviations were identified.
10.
Surveillance Requirements
The NRC inspector reviewed surveillance activities for reactivity limits,
control and safety systems, reactor structure, and radiation ronitoring
and control to determine compliance with TS 4.0.
The NRC inspector
verified that limits regarding excess reactivity, centrol and safety rods
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worth, scram capabilities, and safety systems were not exceeded.
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records of surveillance test results did not indicate any unusual
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conditions.
No violations or deviations were identified.
11.
Experiments
The NRC inspector reviewed the licensee's experiment records and reactor
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logs to determine compliance with TS 3.3.
The NRC inspector determined that the licensee had not introduced any new
experiments in the reactor since the previous inspection.
Experiments
which had been conducted were used with approved procedures under approved
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reactor conditions.
No violations or deviations were identified.
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12.
Fuel Handling Activities
The NRC inspector reviewed the licensee's fuel handling activities to
determine compliance with TS 4.1 and 4.2.
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The NRC inspector verified the licensee had approved procedures for fuel
handling activities and reviewed them for'their-technical adequacy in the
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areas of radiation protection and criticality' safety.
The NRC inspector
determined by record review and discussions with personnel that fuel-
handling operations and startup tests were carried out in conformance with
the licensee's approved procedures.
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No violations or deviations were identified.
13.
Changes-
The'NRC inspector discussed with. licensee representatives and reviewed
reactor maintenance and operation records and determined that no changes
were made since the previous inspection to the facility or procedures that
would require a safety evaluation pursuant to 10 CFR Part 50.59.
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No violations or deviations were identified.
14.
License Conditions
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The NRC inspector reviewed the following license conditions:
2.C.(1) - Maximum Power Level
P..C.(2) - Technical Specifications
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TS 6.9 - Reports
TS 6.10 - Records
TS 6.9.1 states, in part, a routine annual operating report shall be
submitted no later than 90 days following June 30 and provide a
comprehensive summary of the oparating experience.
The NRC inspector determined on March 28, 1988, that the annual operating-
report for the period July 1,1986, through. June 30, 1987, had not been
submitted.
The licensee reviewed their records and also concluded the
annual operating report had not been submitted.
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The failure to submit an annual operating report is considered an apparent
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violation of TS 6.9.1.
(252/8801-01)
15.
Radiation Protection
The NRC inspector reviewed the licensee's radiation protection program to
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determine compliance with 10 CFR Parts 19.11, 19.12, 19.13, 20.101,
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20.104, 20.201, 20.202,-20.203, 20.207, 20.401, 20,403, 20.405, 20.408,
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and 20.409, and TS 4.4.
The NRC inspector reviewed records, interviewed personnel, made
observations, and performed independent' surveys.
The NRC inspector discussed with licensee representatives the results of
the annual radiation survey requirements in TS 4.4.c.
The TS state that
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this survey is required to determine the location of radiation and high
radiation areas corresponding to reactor operating power levels.
The
licensee had performed a survey on December 2, 1987, with the reactor
operating at 3.4 watts and only documented the radiation levels at the six
specific locations which are routinely monitored.
The NRC inspector
stated the annual radiation survey should be a comprehensive survey of the
reactor room.
The licensee acknowledged the NRC inspector's concern and
stated that future radiation surveys would be more detailed.
The NRC inspector noted that all portable radiation survey instrumentation
assigned to the reactor facility including pocket dosimeters were being
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calibrated at an annual frequency in compliance with TS 4.4.a.
No violations or deviations were identified.
16.
Environmental Surveillance / Radioactive Releases
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
maintained.
A licensee representative stated that no liquid effluents have been made
since the last inspection.
The licensee's operations records indicate
that gaseous releases are within 10 CFR Part 20 limits.
No violations or deviations were identified.
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17.
Transportation (Fuel Shipments)
The NRC inspector verified that there had been no fuel shipments since the
previous operational inspection.
No violations or deviations were identified.
18.
Nuclear Materials Safeguards
The NRC inspector reviewed the nuclear material inventory program to
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determine compliance with License Condition 2.B.(2).
The NRC 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
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were defined clearly and understood, and appropriate test procedures were.
being used.
The licensee had not received or shipped any materials since
the previous inspection.
No violations or deviations were identified.
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19.
Emergency Planning
The NRC inspector reviewed the emergency preparedness program to determine.
compliance with the emergency plan requirements.
The emergency plan for the UNM AGN-201M reactor . facility had been. revised
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and submitted to the NRC as part of the application for renewal of
Operating License No. R-102, dated June 2,1986.
The licensee had conducte'd an emergency drill on March 13, 1987.
The NRC
inspector reviewed the results of this drill and the associated
evaluation.
No violations or deviations were identified.
20.
Physical Security
The NRC inspector reviewed the implementation of the licensee's physical'
security plan to determine compliance with 10 CFR Part 73.
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No violations or deviations were identified.
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21.
Exit Interview
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The NRC inspector met with licensee representatives' identified in
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paragraph I at the conclusion of the inspection on March 31, 1988.
The
NRC inspector summarized the scope and findings of the inspection.
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