ML20207F174
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| ML20207F174 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 06/30/1986 |
| From: | Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20207F127 | List: |
| References | |
| 50-252-86-01, 50-252-86-1, NUDOCS 8607220487 | |
| Download: ML20207F174 (9) | |
See also: IR 05000252/1986001
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APPENDIX C
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
F
NRC Inspectio,n Report: 50-252/86-01 License: R-102
Docket: 50-252
Licensee: University of New Mexico (UNM)
Albuquerque, New Mexico
Facility Name: AGN-201/M Reactor (5 Watts)
Inspection At: University of New Mexico
Inspection Conducted: May 19-22, 1986
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Inspectors: / / /[bA () / [h'/A[/ h [
,
R ' E.' Baer,~ Radiation Speciflist, Facilities Date
6/d . Radiological Protection Section
lll NlNdWlbl
B. Murray, Chief', Facilities' Radiological
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Protection Section /
Approved: A/ [[/l,(Y/ / [ 6
B. Murray, Chief, Facilitjts Radiological Ddte '
Protection Section / -
8607220487 860718 2
Inspection Summary PDR ADOCK 0500
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Inspection Conducted May 19-22, 1986 (Report 50-252/86-01)
Areas Inspected: Routine, unannounced inspection of the licensee's
organization, operations and maintenance logs, licensee's internal review and
audit progran, requalification program, operating procedures, surveillance
requirements, experiments, radiation protection, environmental protection,
emergency planning, and physical security plan.
Results: Within the areas inspected, four violations were identified (see
paragraphs 8, 14, and 18).
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DETAILS
1. Persons Contacted
*F. L. Williams, Chairman, Chemical and Nuclear Engineering Department
*R. D. Busch, Reactor Supervisor
G. W. Cooper, Reactor Supervisor
R. Counsellor, Radiation Safety Manager
*B. D. Cox, Chief, UNM Police Department
*R. T. Raymond, Lieutenant, UNM Police Department
A. E. Roybal, Captain, UNM Police Department
*W. L. Tabor, Director, Occupational Safety
R. H. Williams, Assistant Dean, College of Engineering
*D. M. Woodall, Chief Reactor Supervisor
*C. O. Woodstock, Senior Electronics Technician
* Denotes those present during the exit interview on May 22, 1986.
2. Followup on Previously Identified Items
(Closed) Open Item (252/79-02): During the inspection conducted in
November 1979 and reported in report 50-252/79-02, the NRC inspector, when
reviewing the " Manual of Operation," did not find an administrative method
for identifying approved procedures and experiments and for controlling
temporary and permanent changes to these procedures and experiments. It
was also reported that the terms " standard" and " nonstandard" as used to
characterize experiment were not clearly defined and there was no guidance
provided as to the generic types of experiments that could be run without ,
prior approval of the Reactor Safeguards Advisory Committee (RSAC) and the -
Reactor Operations Committee.
The NRC inspectors reviewed the "AGN-201M Reactor Operation and Operator
Training Manual" dated July 1984 and determined that the issues raised in
Inspection Report 79-02 and 82-01, for identifying approved procedures and
the terms " standard" and " nonstandard" which are presently referred.to as
" routine" and "nonroutine" have been included in Section III. This item
is considered closed.
3. Unresolved Items
An unresolved item is a matter about which more information is required in
order to ascertain whether it is an acceptance item, an open item, a
deviation, or a violation.
Unresolved Item (252/8601-05): Radiation Protection Training - This item
involves the training provided to all personnel to satisfy the requirements
of 10 CFR Part 19.12. See paragraph 14 for additional details.
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- 4. Organization and Management Control
The NRC inspectors reviewed the organization and management controls to
determine compliance with Technical Specification (TS) 5.1.
The current organization was verified to be consistent with Section III,
" Administration," of the AGN-201M Reactor Operations and Operator Training
Manual, dated July 1984. The status of licensed operators, membership and
meetings of the Reactor Operations Committee (ROC) and RSAC, and other
matters concerning supervision of the reactor facility were examined. The
NRC inspectors noted that the individual designated " Chief Reactor
Supervisor" was terminating his employment with the UNM and a qualified
individual had been identified to replace him.
No violations or deviations were identified.
5. Operation and Maintenance Logs
The NRC inspectors reviewed the following logs for the period April 1982
through May 1986 to determine compliance with TS 1.0, 2.0, and 5.3:
Reactor Operations Log
Reactor Maintenance Log
Monthly Reactor Inspection Log
All maintenance and operations activities appeared to have been conducted
in a manner consistent with the TS requirements and administrative
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procedures.
No violations or deviations were identified.
6. Internal Audits and Review
j The NRC inspectors reviewed the minutes of meetings conducted by the ROC
- and RSAC and verified that both committees had met semiannually since the
previous 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 committees:
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Technical Specification Requirements
Organization, Staffing, and Licensing
New Facility Operation Manual
New Experiments
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Maintenance, Operations, and Inspection Logs
Excess Reactivity and Control Rod Worths
Procedure Changes
, Radiation Surveys
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Equipment Performance
Security and Security Response
No violations or deviations were identified.
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7. Reactor Operation
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, and
flux distribution. The reactor is also operated during demonstration
courses and the operator requalification program.
On May 21, 1986, the NRC inspectors witnessed startup, operation, and
shutdown of the reactor _during performance of a standard operator
requalification program demonstration.
No violations or deviations were identified.
8. Requalification Training
The NRC inspectors reviewed the licensee's reactor operator
requalification training program for compliance with 10 CFR Part 55,
Appendix A. The NRC inspectors reviewed training documents for currently
licensed individuals against the licensed operators and senior operators
requalification program submitted on December 5, 1973, and additional
information submitted on December 10, 1974, and approved by the Operator
Licensing Branch, USNRC on January 13, 1975, including the recertification
schedule submitted February 21, 1977, and approved on April 12, 1977.
The license had committed in the February 21, 1977, recertification
schedule to perform operational recertification in March and October and
the annual written examination to be given each March. The NRC inspectors
noted from records and the minutes of the January 12, 1983, meeting of the
RSAC that the licensee operator written examination had been extended to a
2 year frequency without approval from the Operator Licensing Branch,
USNRC, and that the scheduled training (operational recertification) after -
March 1981 had not been conducted in October and March for succeeding
training as previously committed.
The licensee's requalification program Section B.5 states that, "A
separate file for each licensed operator or senior operator shall be
established. The attached form will be used to record and certify:
(1) participation in the requalification training' sessions, (2) reactivity
control manipulations, and (3) written and oral e,xamination results.
These files will also contain copies of written examinations administered,
the answers given the licensee, and any additional information regarding
training or requalification of each licensee."
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The NRC inspectors review of the individuai licensed operators files
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indicated that these records were not being maintained for:
(1) participation in requalification training sessions, the last entry
recorded was June 22, 1984, (2) reactivity control manipulations for
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school years 1984-85 and 1985-86 were not recorded, and (3) written
examinations given on January 15, 1986, were not in the individuals file.
The NRC inspectors noted that some written examinations did not indicate
the date when the examination was administered.
The NRC inspectors stated that failure to provide annual written
examinations and scheduled requalification training, and maintain
individual records was an apparent violation of 10 CFR 55, Appendix A and
the licensee's approved requalification program (252/8601-01).
9. Procedures
The NRC inspectors reviewed operating procedures to determine compliance
with the requirements of TS 5.2. The procedures associated with the
reactor are contained in the manual, "AGN-201M Reactor Ope . tion and
Operator Training Manual," dated July 1984. The manual co...ains
procedures for the following categories:
General Desigt Features
Administration
Operating Procedures
Maintenance and Inspections
Emergency Procedures
Technical Specifications
Additional procedures and guides for radiological protection activities
are found in the UNM manual on radiological safety.
No violations or deviations were identified.
10. Surveillance Requirements
The NRC inspectors reviewed surveillance of reactor core, control, and
instrumentation systems to determine compliance with TS 4.0. The NRC
inspectors verified that limits regarding excess reactivity, control and
safety rods worths, core tank design, scram capabilities, and safety
systems were not exceeded. The records of surveillance test results did
not indicate any unusual conditions.
No violations or deviations were identified.
11. Experiments
The NRC inspectors reviewed the licensee's experiment records and reactor
logs to determine compliance with TS 3.0.
The NRC inspectors determined that the licensee had not placed any new
experiments in the reactor since the previous inspection. Experiments
which had been conducted were used with approved procedures and approved
reactor conditions.
No violations or deviations were identified.
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12. Fuel Handling Activities
The NRC inspectors reviewed the licensee's fuel handling activities to
determine compliance with TS 4.2 and 4.3.
The NRC inspectors verified the licensee had approved procedures for fuel
handling activities and reviewed them for their technical adequacy in the
areas of radiation protection and criticality safety. The NRC inspectors
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.
No violations or deviations were identified.
13. Transportation (Fuel Shipments) u
The NRC inspectors verified that there had been no fuel shipments since
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the previous operational inspection.
No violations or deviations were identified.
14. License Conditions
The NRC inspectors reviewed the following license conditions:
3.a - Maximum Power Level
3.c - Authorization of Changes, Tests, and Experiments
3.d.1-d.3 - Reports
3.e - Records
No violations or deviations were identified.
15. Radiation Protection
The NRC inspectors reviewed the licensee's radiation protection program to
determine compliance with 10 CFR Parts 19.11, 19.12, 19.13, 20.101,
20.104, 20.201, 20.202, 20.203, 20.207, 20.401, 20.403, 20.405, 20.408,
and 20.409 and the UNM Emergency Plan.
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The NRC inspectors reviewed records, interviewed personnel, made
observations, and performed independent surveys.
10 CFR Part 20.201(b) states "each licensee shall make or cause to be made
such surveys as: (1) may be necessary for the licensee to comply with the
regulations in this part, and (2) are reasonable under the circumstances
to evaluate the extent of radiation hazards that may be present."
The licensee performed radiation surveys in and around the reactor area on
November 25, 1981, April 30, 1982, November 12, 1982, December 6, 1984,
and April 18, 1985, with the reactor at 5 watts power with a PCN-4 neutron
meter, UNM No. 45015. The date appearing on the calibration sticker was
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illegible, and the licensee was not able to provide any documentation that
the instrument had been calibrated. The licensee also had the following
instruments which had no record of calibrations and past due calibration
stickers.
Model 3 neutron meter UNM No. 159877
PAC-45 alpha meter UNM No. 128236
Model CPMU gamma meter UNM No. 153578
The licensee had documentation of a calibration check performed July 22,
1985, on the PNC-4 and Model 3 neutron meters which recorded the source
used, the distance from source to detector, and the observed count rate
(between 50 and 1000 counts per minute) but did not record the expected
count rate and did not encompass the range (12,000 counts per minute) that
the instrument would be expected to evaluate during full power reactor
operations. It was also noted that the licensee's procedures did not
include a method for converting counts per minute readings into mrem /hr
values. The NRC inspectors also noted that the self-reading pocket
dosimeters and fixed area monitors required in Section 10.3.1 of the
emergency plan were not bein3 routinely calibrated.
The NRC inspectors stated that failure to calibrate radiation monitoring
instruments was considered an apparent violation (252/8601-04) of 10 CFR
Part 20.201(b).
The NRC inspectors discussed with licensee representatives what was
considered an acceptable calibration program including recommendations of
the industry standard ANSI N323-1978.
The NRC inspectors reviewed the course outline for "ChNE-231-Radiation
Safety Engineering" and " Introduction to Radiation Safety" the two courses
presented to students prior to admission to the NELB to verify that these
individuals were receiving all the training required in 10 CFR Part 19.12.
The NRC inspectors were unable to verify that training require in
Regulatory Guide 8.13, applicable provisions of commission regulations,
and reporting responsibilities of individuals were being performed. The
NRC inspectors stated this is considered an unresolved item (252/8601-06)
and will be reviewed further during a future inspection.
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 effluent releases have
been made since the last inspection. The licensee's operation records
indicate that gaseous releases are within 10 CFR 20 limits.
No violations or deviations were identified.
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17. Nuclear Materials Safeguards
The NRC inspectors reviewed the nuclear materials inventory program to
determine compliance with license condition 2.b.
The NRC inspectors reviewed the accountability procedures and practices
records and material status reports. The procedures, practices, and
records were found to be well implemented. Responsibilities and response
requirements 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.
18. Emergency Planning
The NRC inspectors reviewed the emergency preparedness program to
determine compliance with emergency plan requirements.
The emergency plan for the UNM AGN-201M reactor facility had been revised
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on March 11, 1985, to incorporate changes requested by the NRC. This plan
was approved by the NRC on June 11, 1985.
The licensee had conducted an emergency drill on April 30, 1986. The
results of this drill and the associated evaluation was not available for
review during the time of this inspection.
The NRC inspectors discussed with licensee representatives the following
! aspects of the emergency plan:
Section 8.2.1 refers to the type of portable radiation survey
4 instrumentation of sufficient range that is stored in the Nuclear
Engineering 8.aboratory Building (NELB). Section 8.2.3 discusses
self-reading pocket dosimeters for emergency use stored in the NELB
and 10.3.1 discusses the calibration of portable instruments
including pocket dosimeters and fixed radiation monitors.
Section 8.3.2 addresses the Albuquerque fire department response and
transport of injured personnel to the hospital. No provision has
been made to provide for training on the handling of contaminated
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individuals, directing ambulance crews of the contaminated injury
entrance, or notification to the hospital that a contaminated injury
is enroute.
Appendix A will require updating to list the new chief reactor
supervisor and administrator. It was also noted that Region IV,
USNRC was not included on the phone list.
The licensee had a letter of agreement from the city of Albuquerque
fire department to provide fire suppression and emergency medical
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services, but did not have a letter of agreement from the city of
Albuquerque police department to provide services in an emergency.
The licensee had included the emergency response plan dated
September 1982 for the state of New Mexico's Radiation Protection
Bureau, Environmental Improvement Division which is routinely applied
to byproduct material licensees licensed by the state of New Mexico
and transportation accidents but there was no letter of agreement
that this plan would apply to the UNM AGN-201M reactor facility. The
NRC inspectors also questioned whether the tables contained in the
states plan had the correct individuals and telephone numbers listed.
The licensee also included the " procedures for admission and
management of radioactively contaminated patients at
Bernalillo County Medical Center and Cancer Research and Treatment
Center, the University of New Mexico, Albuquerque, New Mexico,
reviewed December 1981." There was no agreement from the hospital
that they would accept contaminated injuries from the AGN-201M
reactor facility and are the individuals and telephone numbers listed
in the plan accurate.
The licensee stated they would review the questions raised by the NRC
inspectors.
No violations or deviations were identified.
19. Physical Security
Included as an attachment to this report.
20. Exit Interview
The NRC inspectors met with licensee representatives at the conclusion of
the inspection on May 22, 1986. The Nf.C inspectors summarized the scope
and findings of the inspection as discussed in paragraphs 8, 14, 17, and
18 of this report.
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