Ro:On 971104,change of Mode Switch from Manual to Pulse Positions Did Not Reliably Switch Between Normal & High Range Signals.Caused by Malfunction of Switch.Applied Switch Cleaning Fluid to SwitchML20198P254 |
Person / Time |
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Site: |
05000113 |
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Issue date: |
11/05/1997 |
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From: |
Williams J ARIZONA, UNIV. OF, TUCSON, AZ |
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To: |
Mendonca M NRC |
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References |
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NUDOCS 9711070040 |
Download: ML20198P254 (2) |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20209A7181999-06-22022 June 1999 Special Rept:On 990607,compliance with Spec 4.6 Was Not Enforced in Procedure Number Uarr 155,monthly Checklist, During Review of TS & Procedures.Caused by Omission of Item from Monthly Checklist.Prepared Revised Version of Uarr 155 ML20196B6021998-11-25025 November 1998 Ro:On 901206,950424 & 970512,deficiencies Occurred in Shipping & Receiving Special Nuclear Matl.Caused by Misunderstanding of Procedure Uarr 127.Committee Discussed Matter in 981103 Meeting & Matter Was Described in Training ML20199B6341997-11-13013 November 1997 Ro:On 971104,malfunction of Mode Switch in Pulse Mode Occurred.Caused by Failure of Mode Switch to Reliably Switch Between Normal & High Range Signals.Removed Rear Casing of Mode Switch & Applied Switch Cleaning Fluid ML20198P2541997-11-0505 November 1997 Ro:On 971104,change of Mode Switch from Manual to Pulse Positions Did Not Reliably Switch Between Normal & High Range Signals.Caused by Malfunction of Switch.Applied Switch Cleaning Fluid to Switch ML20217D1681997-10-0101 October 1997 Ro:On 970930,discovered That Reactor Power Calibr Showed Safety Channels Reading Lower than Actual Power.Cause Indeterminate.Recalibr Power Channels & Issued Instructions to Set Scrams More Conservatively Pending Investigation ML20128P6211996-10-16016 October 1996 Rs:On 960919,reactor Started Up & Operated by RO W/O SRO Supervision.Caused by Personnel Error & Misinterpretation of Procedural Requirements.Ro License Suspended.Procedure Uarr 163 Revised 1999-06-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211G5341999-06-30030 June 1999 Submits Annual Rept, Covering Period 980701 Through 990630 for Activities of Triga Mark I Reactor.With ML20209A7181999-06-22022 June 1999 Special Rept:On 990607,compliance with Spec 4.6 Was Not Enforced in Procedure Number Uarr 155,monthly Checklist, During Review of TS & Procedures.Caused by Omission of Item from Monthly Checklist.Prepared Revised Version of Uarr 155 ML20196B6021998-11-25025 November 1998 Ro:On 901206,950424 & 970512,deficiencies Occurred in Shipping & Receiving Special Nuclear Matl.Caused by Misunderstanding of Procedure Uarr 127.Committee Discussed Matter in 981103 Meeting & Matter Was Described in Training ML20237C9921998-06-30030 June 1998 Annual Rept Covering Period 970101-980630 for Activities of Triga Mark I at Univ of Az,Tucson,Az.Supporting Documentation,Encl ML20198B2201997-12-18018 December 1997 Safety Evaluation Supporting Amend 17 to License R-52 ML20199F1971997-11-13013 November 1997 Deficiency Rept Re Malfunction of Mode Selector Switch. Action Will Be Reviewed by Reactor Committee for Facility ML20199B6341997-11-13013 November 1997 Ro:On 971104,malfunction of Mode Switch in Pulse Mode Occurred.Caused by Failure of Mode Switch to Reliably Switch Between Normal & High Range Signals.Removed Rear Casing of Mode Switch & Applied Switch Cleaning Fluid ML20198P2541997-11-0505 November 1997 Ro:On 971104,change of Mode Switch from Manual to Pulse Positions Did Not Reliably Switch Between Normal & High Range Signals.Caused by Malfunction of Switch.Applied Switch Cleaning Fluid to Switch ML20217D1681997-10-0101 October 1997 Ro:On 970930,discovered That Reactor Power Calibr Showed Safety Channels Reading Lower than Actual Power.Cause Indeterminate.Recalibr Power Channels & Issued Instructions to Set Scrams More Conservatively Pending Investigation ML20216D4731997-08-13013 August 1997 Annual Rept Covering Period Jul 1996-June 1997,for Activities of Triga Mark I Reactor at Univ of Az,Tucson,Az ML20128P6211996-10-16016 October 1996 Rs:On 960919,reactor Started Up & Operated by RO W/O SRO Supervision.Caused by Personnel Error & Misinterpretation of Procedural Requirements.Ro License Suspended.Procedure Uarr 163 Revised ML20059E8061990-08-29029 August 1990 Annual Rept for License R-52 for Jul 1989 - June 1990 ML20248A9711989-09-15015 September 1989 Rev 1 to Operator & Senior Operator Requalification Program for Univ of Arizona Research Reactor ML20246N7601989-08-31031 August 1989 Annual Rept Covering Period Jul 1988 - June 1989 for Activities of Triga Mark I Reactor ML20204F5311988-10-19019 October 1988 SAR Univ of Arizona Triga Mark I Research Reactor ML20204F4341988-10-17017 October 1988 Operator & Senior Operator Requalification Program ML20209H5671986-08-27027 August 1986 Annual Rept for Triga Mark I Reactor at Univ of Arizona,Jul 1985 - June 1986 ML20135A9281985-08-26026 August 1985 Annual Rept for Jul 1984 - June 1985 1999-06-30
[Table view] |
Text
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t4UCLE AR Et4 Git 4EERIl4G TEL1520-621-8096 tiov 05.97 14: 18 No.003 P.01 j'b - //1 l
Date: 5 Nov 1997 To: Attention of Marvin Mendonca, By Telefax,(301) 415 3313, USNRC, One White Filnt North 11555 Rockville Pike Rockvlile, MD 20852 2738.
From: John O. Willinmn, Re .: tor Laboratory Director, Engineering Building 20, University of Arizona, Tucson, AZ 857210020 (620) 621 9729 Ret Reportable occunence, trar.smitted within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The occurrence documented on the following page was reported by telephone to you at 1345, local time, today. Mr. Steven Holmes' meunge system also received my call.
The tequired telegraphic report is submitted via telefax herewith, for recording on our License Docket. A fuller written report will follow within 10 days.
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_. _ _ _. _ _ _ .m HUCLEGR ENGINEERING R EL:520-621-8096 Nov 05.97 14: 10 tio.003 P.02 FACILITY I,1CP.NSE R 52 t ,
Malfunction of Mode Switch in Pulse Mode i
- Prcliminary Report. November 5,1997
O'i November 4,1997, a pulse was performed with the mode switch in its Pulse High I netting and with the transient rod anvil net for a $1.75 pulse. De transient rod operated normally, fuel temperature rise was recorded showing energy deposition in the range r
, expected for a normal pulse and the timer scram operated normally. No valid indk.ation '
appeared, however, for the peak tenctor power or the Integrated pulse energy. %e right ,
safety channel lndicated a trip on reactor power. :
A digital data acquisition system connected to the right safety channel showed that the algnal on that channel dispinyed a normal reactor perlod of approximately 11 ms, but then !
saturated. This showed that the channel was connected to a valid Indicatlou of reactor 1
[ power level from the km chamber that is normally connected in steady state mode, not the j high range ion chamber which should be selected in pulse mode. De trip on the right
- bafety channel was attributed to power in excess of 110 kW, which is the s'cady state limit.
Testing of the mode switch revealed that changing the switch from its manual to pulse positions did not rcilably switch between the normal and high range alsnals. De problem
^
was corrected by app!kation of switch cleaning fluid. After this w as done the system appeared to behave normally. He reactor was then operated at 95 kW steady state while i the high range channel was calibrated and shown to behave normally.- A pulse was then -
performed and normal indications were found on all channels.
A malfunction of the mode switch was the cause, it resulted in failure to pick a relay
- which switches from the normal to the high range channel when pulse mode is selected, and which also switches in the nyt circuitry that indicates integrated pulse energy. The system failed safe caum. 4.ictuation of reactor scram at 110 kW. He reactor did not operate outside its normal envelope, and there was no threat to health or safety of the public, f.f J. O. Williams. Reacer laboratory Director ,
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