IR 05000113/1982001
| ML20053C783 | |
| Person / Time | |
|---|---|
| Site: | 05000113 |
| Issue date: | 05/14/1982 |
| From: | Kirsch D, Willett D, Zwetzig G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20053C778 | List: |
| References | |
| 50-113-82-01, 50-113-82-1, NUDOCS 8206020557 | |
| Download: ML20053C783 (6) | |
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UNITED STATES
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REGION V
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WALNUT CREEK, CALIFORNIA 94596 May 17,1932 Docket No. 50-113 University of Arizona College of Engineering Tucson, Arizona 85721 Attention:
Dr. R. H. Gallagher, Dean College of Engineering Gentlemen:
Subject: NRC Inspection of TRIGA Fark I Facility This refers to the routine inspection conducted by Messrs. D. F. Kirsch and D. J. Willett of this office on May 5, 6 and 7,1982, of activities authorized by NRC License No. R-52, and to the discussion of our findings held by Mr. Kirsch with you and other members of your staff at the conclusion of the inspection.
Areas examined during this inspection are described in the enclosed inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspectors.
l No items of noncompliance with NRC requirements were identified within the scope of this inspection.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room unless you notify this office, by telephone, within ten days of the date of this letter and submit written aoplication to withhold information contained therein within thirty days
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of the date of this letter.
Such application must be consistent with the requirements of 2.790(b)(1).
Should you have any questions concerning this inspection, we will be glad to discuss them with you.
Sincerely, i
e D. M. Sternberg, Chief Reactor Operations Projects Branch
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University of Arizona-2-May 17, 1982 Enclosure:
Inspection Report
No. 50-113/82-01
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U. S. NUCLEAR REGUL\\ TORY COMMISSION
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REGION V
Report No.
c;0-ll 3/82-01
Docket No.
50-113
License No.
R-52
Safeguards Group
Licensee:
University of Arizona
College of Engineering
Tucson, Arizona 85721
Facility Name:
Triga Mark I
inspection at:
Tucson, Arizona
Inspection conducted:
May 5-7, 1982
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Inspectors:
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D. F. Tirsch, Reactor Inspector
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Date Signed
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D.J.Wille(t,ReactorInspector
Date Signed
Date Signed
Approved By:
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@G. I3. Ntzig, Chief, Reactor Projects Section 1
Date Signed
Reactor Operations Projects Branch
Su= mary:
Inspection on May 5-7, 1982 (Report No. 50-113/82-01)
Areas Inspected: Routine, unannounced inspection of follow up on open items and
items of noncompliance; organization; logs and records; review and audit; requali-
fication training; procedures; surveillance; experiments; and independent
inspection effort. The inspection involved 22 inspector hours onsite by two
NRC inspectors.
Results:
No items of noncompliance were identified.
RV Fcrm 219 (2)
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DETAILS
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1.
Persons Contacted
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- R. H. Gallagher, Dean, College of Engineering
- R. L. Seale, Head, Department of Nuclear and Energy Engineering
- G. W. Nelson, Director, Reactor Laboratory.
- B. D. Ganapol, Chairman, Reactor Committee
H. Doane, Reactor Supervisor
- Denotes those present at exit interview.
E.
Follow-up on Items of Noncompliance'
a.
(Closed) Noncompliance (50-113/80-01-01): Failure of Reactor
Committee to meet quarterly. By letter dated April 25~, 1980, the
licensee stated that future meetings would be held quarterly
as required by Technical Specifications. The. inspectors verified
that the licensee had since. held Reactor Canmittee meetings on a
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quarterly basis.
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b.
(Closed) Noncomoliance (50-113/80-01-03): Failure to operate the
facility ventilation system as required by Technical Specifications.
The inspectors observed, by sampling of the preliminary checklists,
that verification of ventilation system operation was conducted each
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time the Preliminary Checklist was completed in preparation for
critical operation. The Preliminary Checklist contains a requirement
to verify ventilation system operation. This requirement was also
a topic of a training meeting held May 5, 1982.
3.
Follow-up on Previously Identified Open Items
a.
(Closed) Open Item (50-113/80-01-02):
Procedures Manual did not
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contain procedures for two Technical Specification required
surveillances. The inspectors reviewed the procedures manual
and found that procedures for determination of control rod worth
and calorimetric calibration of safety channels had been included in
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the procedures manual.
b.
(Closed) Open Item (50-113/80-01-04):
Safety evaluations for
facility changes, tests, or untried experiments. The inspectors
examined the licensee's controls governing internal reviews conducted
pursuant to 10 CFR 50.59 and found the system adequately complies
with regulatory requirements.
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4.
Organization, Logs, and Records
The inspectors verified that the facility operating organization was
consistent with technical specification requirements.
It was further
verified by observation and inspection of the operating records, on a
sampling basis, that the minimum staffing required for operation was in
accordance with technical specification requirements. The inspectors
also examined representative samples of the following logs and records,
generated subsequent to March 1980, for evidence of significant problems:
Monthly Checklist
Annual Checklist
preliminary Checklist
Critical Approach Checklist
Termination Checklist
Pulsing Checklist
Reactor Operations Log
Fuel Element Inventory
Reactor Upgrade and Instrument Log
Reactor Upgrade Maintenance Log
Irradiation Request and M3terial Transfer Log
Management Log Review Documentation-
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No significant problems were identified by the examination of representative
samples of these records.
The inspector examined the applicable records t$ determine, on a sampling
basis, if the following maintenance activities were being performed-in.
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accordance with regulatory or administrative requirements:
Calibration of Continuous Air Monitor
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Calibration of Water Monitor
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Calibration of Safety Channels
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Replacement of Demineralizer Filters and Resins
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No items of noncompliance or deviations were identified.
5.
Review and Audit
The membership of the Reactor Committee was determined through
discussions with the licensee's representatives and the Reactor
Committee Chairman. The discussions indicated that, while the membership
conformed to Technical Specification requirements, letters appointing
each member were not centrally filed. The licensee agreed to establish
a file documenting Reactor Connittee membership appointments.
The inspectors reviewed the minutes of Reactor Committee meetings held
from September 1980 through March 1982. The minutes indicated
compliance with the requirements regarding meeting frequency and
quorum.
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The inspectors examined one facility modification which had been completed.
This modification involved the replacement of a p)wer supply for the
right safety channel high voltage. The matter had been reviewed and
approved by the Reactor Committee and appropriately documented.
No items of noncompliance or deviations were identified.
6.
Operator Requalification Training
The inspectors reviewed representativ< samples of requalification
training records and operating logs.
Based on this review, and
discussions with two operators, the inspectors concluded that training,
training records, reactivity manipulations, and supervisory evaluations
appeared to conform to regulatory requirements.
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No items of noncompliance or deviations were identified.
7.
Procedures
The inspector examined the facility Administrative ' Procedure UARR100
for compliance with technical specifications requirements regarding
Reactor Committee activities. The administrative procedure appeared
deficient in the implementation of the following requirements of technical
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specifications:
a.
The responsibilities assigned to the Reactor Committee by Technical
Specification paragraphs 6.2.b, 6.3., 6.4 and 6.5 were not adequately
included in Procedure UARR100.
b.
The Reactor Committee composition requirenents of Technical
Specification paragraph 6.2.c were not adequately defined in
UARR100.
For example, the procedure did not reference or name
the Reactor Committee Chairman, member' ship or designated alternates.
The inspector, however, observed that the Chairman and membership had
been assigned responsibilities by letters although those letters were
not in any central location.
It was further observed that membership
assignments had been carefully chosen to consist of a multi-disciplined,
highly qualified representation.
c.
The requirements of Technical Specification paragraph 6.2.d (regarding
a written statement of committee authority, subject preview, and
administrative provisions) were not adequately included in UARR100.
The Reactor Committee Charter, adopted April 26, 1976, contained many
of the technical specification requirements, however, the charter
was not referenced by UARR100 and was not a controlled document.
In addition, the technical specification requirement for meeting
minutes of Reactor Committee meetings was not included as a requirement
of UARR100, although the licensee had prepared detailed minutes
documenting committee meeting '
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d.
The requirements of Technical Specification paragraph 6.2.f, regarding
Reactor Committee meeting frequency, were not adequately included in
UARR100.
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The licensee agreed to evaluate the identified administrative procedure
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deficiencies and effect appropriate resolution. This area will be examined
further during a future inspection. -(50-113/82-01-01)
The inspectors observed that a' controlled set of approved procedure was
available to operators in the control area.
No items of noncompliance or deviations were identified.
8.
Surveillance
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The inspectors examined the licensee's methods.for complying with
technical specification limiting conditions for operation contained
in paragraphs 3.4, 3.6 and 4.0.
That the licensee had complied with
the applicable requirements was verified by examination of appropriate
checklists, records, and surveillance documentation.
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No items of noncompliance or deviations were identified
9.
Experiments
The inspectors examined documentation of Reactor-Committee review and
approval of three experiments performed since March 1980.
These experiments
involved measurement of void coefficient of reactivity, irradiation
of various samples of material, and local area radiation measurements
resulting from a fuel element exposed in air. The inspectors
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determined that the Reactor Committee had appropriately reviewed
and approved the experiments. The review suitably considered regulatory
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requirements, potential hazards, radiological factors, and reactivity
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effects.
No items of noncompliance or deviations were identified.
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10.
Independent Inspection Effort
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The inspectors examined the cleanliness and or' der of the control-and
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reactor areas and observed that the areas appeared well ordered and
very clean.
By discussions with licensee management and review of-documentation
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the inspectors determined that management had exercised a considerable
effort in the direction and oversight of reactor operations and
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administrative control.
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No items of noncompliance or deviations were, identified.
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11.
Exit Interview
The inspectors met with licensee representatives (denoted in paragraph 1)
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at the conclusion of the inspection on May 7,1982, and summarized
the inspection scope and findings.
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