ML20196A366
| ML20196A366 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 06/23/1988 |
| From: | Verneston W FLORIDA, UNIV. OF, GAINESVILLE, FL |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8806300022 | |
| Download: ML20196A366 (5) | |
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NUCLEAR ENCINEERING SCIENCES DEPARTMENT Nuclear Reactor Facility University of Florido e
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.Swimm Clutch Current Indicating Lamp Failure Final (14 Day) Report Nuclear Regulatory Commission Suite 2900 i
101 Marietta Street, N.W.
Atlanta, Georgia 30323 Attention:
J. Nelson Grace Regional Adminis trator, Region II Re:
University of Florida Training Reactor Facility License: R-56, Docke t No. 50-83 Gen tlemen:
Pursuant to the reporting requirements of paragraph 6.6.2(3)(c) of the UFTR Technical Specifications, a description of a potential abnormal occurrence as defined in the UFTR Technical Specifications, Chapter 1 is described in this 14-day report to include NRC notification, occurrence scenario, evaluation of consequences, corrective action and current s tatus. The potential promptly re-portable occurrence involved burnout of the clutch current indicating lamp for control blade Saf ety-2 at full power.
NRC Notif ication The Executive Committee of the Reactor Saf ety Review Subcommittee (RSRS) re-viewed this occurrence on June 13, 1988 and concluded that it is a potential abnormal occurrence as defined in UFTR Technical Specifications, Chapter 1, The Executive Committee also concurred with management res tart approval sub-ject to NRC concurrence. The RSRS then ins tructed NRC notif ication as per Sec-tion 6.6.2 of the UFTR Tech Specs. This notification was carried out by both Mg telephone to Mr. Paul Frederickson and a following telecopy on June 13, 1988 xo (see Attachnent I).
go Ir:itial Event Scenario oo
$j On Friday, June 10, 1988 at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> af ter approx finately 5 1/2 hours of sam-1 ple irradiation at f ull power (supporting neutron activation analys is) in pro-g vico gress, the Control Blade Saf ety-2 clutch indicating lamp (see marked section 8$
of Attachnent II; Figure 7-1, Overall UFTR Ins trutnentation and Scram Logic ggy Diagram) burned out, dropping Control Blade Saf ety-2 f rom 56% witMrawn to the ts co f ully inserted position. The reactor operator at the controls responded j
promptly by conducting an unscheduled reactor shutdown per SOP-A.4, Reactor W
Slutdown with the reactor secured at 1722 hours0.0199 days <br />0.478 hours <br />0.00285 weeks <br />6.55221e-4 months <br />,
j Evaluation of Consequences "k l Reactor s taf f and adminis tration including Director W.G.
Verne tson concluded there was no compromise to reactor saf ety in this event, nor was there any
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impact on personnel radiation doses. All control and saf ety aystems responded gg Properly.
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Nuclear Regulatory Commission June 24, 1988 Page Two Based on evaluations of this event, res tart was recommended f ollowing replace-ment and retest of all clutch indicating lamps including associated required surveillances such as control blade drive and drop time checks. Discussion and review of Technical Specification requirements (see Attactnent III f or applic-able sections of Technical Specifications) indicated thatt 1.
Congrol Blade Saf ety-2 at the 56% withdrawn position is worth about 132 x 10 A k/k, or 41.9 dollars of reactivity.
2.
A special report is required f or an uncontrolled or unanticipated changi in reactivity greater than one dollar (excepting reactor trips f rom known causes - this event is a gravity drop of one control blade into the reactor as a result of terminating power to the blade drive magnetic clutetes, but not a Reactor Trip as defined in Technical Specifications ;
see Attachment III).
Corrective Action immediate corrective action consisted of replacing the burned out clutch cur-rent indicating bulb to include the necessary control blade drive and drop time checks. All were successful so the reactor was res tored to operating s tatus on June 15, 1988.
Although there are no radiological or saf ety consequences of this event, such f ailures are to be avoided. Therefore, since a clutch indicating lamp f ailure occurred las t year (at a hutdown conditions), the f requency of preventive clutch current indicating lamp replacement will be increased f rom annual ver-sus semi-annual preventive maintenance. This action is in agreement with pre-vious management evaluations and discussions with the RSRS Executive Committee on June 13, 1988. This actin is expected to reduce significantly the likeli-hood of recurrence of this f ailure event.
Current Status Since res tart on June 15, 1988, there has been no recurrence of f ailure of any clutch current indicating lamp.
Sincerely, A
William G. Vernetaon Director of Nuclear Facilities WGV/ps At tac hmen ts h % b d.(d b o WaT Q Notary Late cct P.M. M ey Ete:y NL. State of IbrUa ~
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Reactor Saf ety Review Subcommittee Document Control Desk Mr (wJUa byn Mmh 22, M wu.s tw. im f.%
NUCLEAR ENGINEERING SCIENCES DEPARTMENT Nuclear Reactor Facility y
University of Florida i
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ATTACHMENT I e vr nauaan m*
' mne(voants.1429.t.t.a s43xi June 13, 19011 Nuclear Regula tory Commission Suite 2900 101 Marietta Street, N.W.
Atlanta, GA 30323 Attention:
J. Nelson Grace Regional Administrator, Region II t
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University of Florida Tr aining Reactor racility License: R-56, Docket No. 50-03 As per telephone call of 13 June 1980, relative to failurn of control Blade Safety 2 clutch status indicating lartp, the Reactor Safety Review Subcommittee has reviewed and concluded that this event constitutes a potentially reportatile occurrence per Toch-nical Specifica tions 6.6.2( 3)(d). The RSRS has instructed NRC notification per Section 6.6.2 of the Uf'TR Technical Specifica-tions.
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i ATTACHMENT III University of Florida Technical Specifications 6.6.2 Special Reports There shall be a report not later than the following working day by telephone and confirmed in writing by telegraph or similar conveyance to the Commission, to be followed by a written report that describes the cii umstances of the event within 14 days of any of the following:
(3) any of the following:
(d) an unanticipated or uncontro' led change in reactivity greater than one dollar (Reactor trips resulting from a known cause are excluded.)
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j Reactor Trip:
A reactor trip is considered to occur whenever one of the two following actions take place:
l (1)
Rod-Orop Trip -- a gravity drop of all control blades into the reactor core as a result of terminating electrical power to the blade drive magnetic clutches.
(2)
Full-Trip -- the water is dumped from the reactor core by the safety actuation of the dump valve in addition to the rod-drop trip.
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