IR 05000407/1980002
| ML19323B333 | |
| Person / Time | |
|---|---|
| Site: | University of Utah |
| Issue date: | 03/21/1980 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19323B325 | List: |
| References | |
| 50-407-80-02, 50-407-80-2, NUDOCS 8005120248 | |
| Download: ML19323B333 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
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IE Inspection Report No. 50-607/80-02 Docket No. 50-407 License No. R-126 Licensee:
University of Utah College of Engineering Salt Lake City, Utah 84112 i
Facility Name:
University of Utah Triga, Mark 1 i
l Inspection at:
University of Utah, Salt Lake City, Utah
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Inspection Conducted:
March 4-6, 1980 Inspectors:
7. [,
M g 24 Fo M. W. Dickerson, Reactor Inspector Date l
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Reviewed by:
7- [.
b 3-28-90 i
G. L. Madsen, Chief. Reactor Operations and Date
Nuclear Support Br nch Inspection Summa ry
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Inspection on March 4-6, 1980 (Report No. 50-407/80-02)
t Areas Inspected:
Routine, unannounced inspection oi: Organization, Logs and Records; Review and Audits; Requalification Training; Procedures;.
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Surveillance; Experiments; Radiation Control; and Follow-up on previously
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identified open items.
The inspection involved 24 inspector-hours on-site i
by one (1) N20' inspector, u
l Results: Of the eight (8) areas inspected no items of noncompliance were l
found in seven (7) areas.
Two items of noncompliance (Infraction -
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failure tn comply with Technical Specifications, paragraph 5) were identified during inspection of the remaining area.
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i DETAILS I
1.
Persons Contacted l
University of Utah
Dr. R. E. Turley, Reactor Administrator
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j Dr. G. M. Sandquist, Reactor Supervisor Dr. R. C. Pendleton, Radiation Safety Officer
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C. Jensen, Senior Reactor Engineer
T. R. Downard, Assistant Radiological Health Officer
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Licensee Action on Previous Inspection Findings
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(Open) Unresolved Item (50-407/78-02):
Formal and Detailed Surveillance Procedures.
Surveillance Procedures and data sheets, such as those for control rod drop reactivity worths and power calibration have not j
been completed.
The licensee had previously agreed that the appropriate
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procedures would be prepared. However, since none have been prepared j
this item have been escalated to an unresolved item.
j (Close) Unresolved Item (50-407/7901-1):
Calibration of Reactor
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Laboratory Survey Instruments.
Survey instruments whose Serial Nos. are 34550 and 1197 have been removed from service and those instruments in service have been calibrated.
(Close) Open Item (50-407/7901-1):
Organization and Retrieval of
i Radiation Control Records.
Records were organized and were readily retrievable.
(Close) Open Item (50-407/7901-2): Acceptable Documentation relative to
procedure review and approval by the Reactive Safety Committee.
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Procedures reviewed and approved by the Reactor Safety Committee dur.ng the past year were readily determined by the inspector.
3.
Reactor Organization, Logs and Records Within the area of Organization the inspector observed that the l
facility organizatica is consistent with the Technical Specifications.
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The following logs and records for the period January 26, 1979 thru
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February 11, 1980 were reviewed:
(a) Reactor Operations Log, Volumes 5, 6 and 7.
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(b) Reactor Startup and Termination Check Lists B1, B2, and B3.
(c)
Preliminary Procedures Log.
(d) Maintenance Log.
(e) Monthly Inspection Sheets B4 and B5.
(f) Fuel Inventory Sheets.
In addition to the above, the inspector also reviewed applicable sections of the " Nuclear Engireering Laboratory Operations Manua'." as reviewed ano approved by the Reactor Safety Committee (RSC).
The inspector noted that the core configuration had been changed to core configuration No. 7 by the replacements of the Aluminum clad elements with those clad with stainless steel.
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No items of noncompliance or deviations were identified.
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Procedures The inspector reviewed the procedural requirements as required by the Technical Specification and determined that procedures relative
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to the following areas had been reviewed and approved by the Reactor
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Safety Committee:
a.
Startup, Operation, and shut down of the reactor.
b.
Installation or removal of fuel elements, control rods, experiments and experimental facilities.
Actions to be taken to correct specific and forseen potential c.
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i malfunctions of systems or components.
d.
Emergency procedures,
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e.
Maintenance procedures.
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f.
Surveillance procedures.
Procedures for the receipt, storage and loading for new core configuration No. 7 contained in the preliminary procedures log l
were retiewed by the inspector.
The procedures approved by the RCS were:
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Procedure for unloading new fuel, approved April 12, 1979
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Procedure for transfer of fuel from storage to reactor storage, approved April 26, 1979.
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I Additionally, the procedure for Biannual fuel inspection, approved
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January 31, 1980 was also reviewed.
l 5.
Surveillance
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By review of the logs and records noted previously the inspector i
determined that all required surveillance activities, except those for control rod inspection and channel calibration had been performed
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in accordance with Technical Specifications.
During this review the inspector determined that a visual inspection of
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the control rods had not been performed since March 1977, a period
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of three years.
T/S 4.2.c requires that the control rods be visually
inspected for deterioration at intervala not to exceed two years.
Contrary to this, the control rods had not been inspected for three years.
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The licensee was informed that this was an item of noncompliance at
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the infracti,a level.
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The review also resulted in the determination by the inspector that a
i channel calibration of the power level monitoring channels had not been made since January 8,1979, a period of fourteen months exceeding the requirements of T/S 4.3.6 which require that a channel calibration
shall be made of the power level monitoring channels by either nuclear or calorimetric methods semiannually, but at intervals not
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to exceed 8 months. The licensee was informed that failure to perform
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the calibration was an item of noncompliance at the infraction level.
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The inspector also expressed concern that the surveillance activities are not completed utilizing formal procedures, where required, and that adequate records ~and data relative to completion of surveillance
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activities are not maintained.
This had previously been discussed l
with the licensee (R0 7802 & 7901) who indicated that appropriate
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procedures would be prepared.
However, since this has not been done
this previously open item is being escalated to an unresolved item.
l The inspector had no additional questions in this area.
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6.
Requalification Training
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l At the present time there are four licensed operators at.the
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facility, one of whom was the reactor supervisor and as such is
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exempt from the requalification program.
The written examination and reactor manipulation records for the two operators who remained under the requalification program were examined and found acceptable. One additional operator must be given the examination in March 1980 to
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remain qualified.
I No items of noncompliance or deviations were identified.
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7.
Reviev and Audit The minutes of the licensee's Reactor Safety Committee (RSC) Meetings
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were reviewed.
The responsibilities of the RSC are outlined in Technical Specifications 6.1.b and 6.2, Sections 1 and 3.4 of the Operations Manual and are further amplified by " Reactor Safety Committee - Rules and Procedures" dated September 29, 1977.
Records indicated that the RSC met quarterly on the following dates:
March 29, 1979; June 28, 1979; September 26, 1979; and December 20, 1979.
No items of noncompliance or deviations were identified.
8.
Experiments The experiments performed during the period January 24, 1979 to March 4, 1980, involved only irradiations that had been approved,as class 1 experiments.
The experiments had been completed, reviewed, and approved in accordance
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i with Technical Specifications and Section 2 of the Nuclear Engineering Laboratory Operations Manual.
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No items of noncompliance or deviations were identified.
9.
Annual Operating Report The inspector reviewed the annual operating report for the University of Utah Triga reactor for the period July 1, 1978 through June 30, 1979.
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No items of noncompliance or deviations were identified.
10.
Radiation Control l
The inspector reviewed the facilities procedures, posting requirements, i
radiation area markings, personal monitoring devices, and reviewed the following records:
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a.
Air sampling data; February 1979 - February 1980, b.
Water sampling data, February 1979 - February 1980, c.
Calibration Records (Instruments), February 1,1979 - October 11, 1979, d.
Radiation Survey Log, January 31, 1979 - February 27, 1980, Records of external radiation exposure, November 1979 - January 1980.
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No items of noncompliance or deviations were identified.
11.
IE Bulletins / Circulars The inspector verified by record review, observation, and discussion
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with representatives of the licensee, the actions taken in response to IE Bulletins / Circulars.
The following Circular was reviewed:
79-09 Occurrences of split or punc.ced regulation diaphragms in certain self-contained br.athing apparatus - None utilized at the reactor.
Information passed on to fire fighting unit.
The following Bulletin was reviewed:
79-19 Packaging of Low-Level Radioactive Waste for Transport and Burial - The requirements of the bulletin as they apply to Operating License R-126 (as well as Licensee R-25, AGN-201) were reviewed in accordance with TI 2840/1. The specific provisions of 79-19 do not apply to the University Laboratory since the waste generated there is transferred to the Radiological Health Department for Transport.gd Burial under the University of Utah broad license 43-1884-1.
It is under the broad license that packaging, transport and burial would be provided.
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12.
Exit Interview
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An exit interview was held with representatives of the licensee on March 4, 1980, following completion of the inspection.
At the
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inte rview, the inspector discussed the findings indicated in the previous paragraphs.
The licensee acknowledged these findings.