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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20085K9771991-10-25025 October 1991 Special Rept:On 911023,roll Pin Cracking Observed in Fuel Handling Cones.Cause Unknown.Reactor Operations Suspended Until Cause of Pin Cracking Determined & Appropriate Replacement for Pins Identified & Installed ML20215L5431987-06-17017 June 1987 Special Rept:On 870603,during Normal Startup of Reactor,One Linear Percent Channel Failed to Indicate Power Level on Panel Meter.Caused by Malfunction of Test Switch.Maint Practice Changed to Include Cleaning of Test Switch ML20148E0131978-09-27027 September 1978 Ro:On 780914,shim-safety Rod UTR-10 Failed to Insert During Manual Scram.Caused by Loose Position Potentiometer Mounting Nut.Lock Washer Added to Potentiometer Mounting Hardware 1991-10-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20209F6521999-06-30030 June 1999 Annual Operations Rept for Iowa State Univ UTR-10 Reactor for 980701-990630. with ML20198R2541999-01-0606 January 1999 Rev 0 to Draft Decommissioning Plan for Iowa State Univ UTR-10 Reactor ML20198R2651999-01-0606 January 1999 Rev 0 to Characterization Rept for Iowa State Univ UTR-10 Reactor ML20236P0781998-06-30030 June 1998 Annual Operations Rept Iowa State Univ UTR-10 Reactor for Jul 1997-June 1998 ML20217H3131998-03-30030 March 1998 Safety Evaluation Supporting Amend 12 to License R-59 ML20198R2781998-01-0606 January 1998 Appendices to Characterization Rept for Iowa State Univ UTR-10 Reactor ML20151K2381997-06-30030 June 1997 Annual Operations Rept IA State Univ UTR-10 Reactor for 960701-970630 ML20132B0701996-12-13013 December 1996 Safety Evaluation Supporting Amend 11 to License R-59 ML20116B8781996-06-30030 June 1996 Annual Operations Rept for Iowa State Univ UTR-10 Reactor 950701-960630 ML20092B4351995-06-30030 June 1995 Annual Operations Rept Iowa State Univ UTR-10 Reactor Jul 1994 - June 1995 ML20084V1961995-05-26026 May 1995 Requalification Program for Licensed Operators of UTR-10 Facility ML20070J5221994-06-30030 June 1994 Annual Operations Rept IA State Univ UTR-10 Reactor 930701- 940630 ML20058F7921993-11-29029 November 1993 Safety Evaluation Supporting Amend 10 to License R-59 ML20046A3891993-06-30030 June 1993 Annual Operating Rept for IA State Univs UTR-10 Reactor, for 930701-0630.W/930720 Ltr ML20099G9041992-06-30030 June 1992 Corrected Annual Operations Rept for Iowa State Univ, for Jul 1991 Through June 1992 ML20085N3931991-10-29029 October 1991 Deficiency Rept Re Discoloration of Low Enrichment U Fuel Plate Cladding.Initially Reported Via 911029 Telcon.Order Prohibiting Further Operation of Reactor Issued on 910920 & Plate Removed.Investigation Into Cause Underway ML20085K9771991-10-25025 October 1991 Special Rept:On 911023,roll Pin Cracking Observed in Fuel Handling Cones.Cause Unknown.Reactor Operations Suspended Until Cause of Pin Cracking Determined & Appropriate Replacement for Pins Identified & Installed ML20077L2041991-06-30030 June 1991 Annual Operations Rept for Iowa State Univ Research Reactor for Jul 1990 to June 1991 ML20059J9081990-09-12012 September 1990 Safety Evaluation Supporting Conversion Order for License R-59 to Allow Facility to Convert from High Enriched to Low Enriched U Fuel ML20058L3511990-06-30030 June 1990 Annual Operations Rept for Iowa State Univ Research Reactor for Jul 1989 - June 1990 ML20247N1461989-06-30030 June 1989 Annual Operations Rept for Iowa State Univ Research Reactor, 880701-890630 ML20151Q5931988-06-30030 June 1988 Annual Opeations Rept for Iowa State Univ Research Reactor for Jul 1987 - June 1988 ML20236C2301987-06-30030 June 1987 Annual Operations Rept for Jul 1986 - June 1987 ML20215L5431987-06-17017 June 1987 Special Rept:On 870603,during Normal Startup of Reactor,One Linear Percent Channel Failed to Indicate Power Level on Panel Meter.Caused by Malfunction of Test Switch.Maint Practice Changed to Include Cleaning of Test Switch ML20204F2251986-06-30030 June 1986 Annual Operations Rept for Jul 1985 - June 1986 ML20148E0131978-09-27027 September 1978 Ro:On 780914,shim-safety Rod UTR-10 Failed to Insert During Manual Scram.Caused by Loose Position Potentiometer Mounting Nut.Lock Washer Added to Potentiometer Mounting Hardware 1999-06-30
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- Department of Nuclear Engineering 261 Sweeney Hall IOWA STATE ^=# io- 5*"
UNIVERSITY T* phone 515 2m TRIORITY ROUTIf:G Docket No. 50-116 ~
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U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement - Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Re: Malfunction of a Reactor Safety Channel The enclosed "Special Report" was written to describe an interesting failure and is submitted for your information. The event described is classified as an " unplanned shutdown", but the malfunction that caused the shutdown deserves some discussion.
As described in the report, the failure was traced to a manually operated switch used to test the function of a scram circuit in a one-of-two safety system prior to startup. The switch failed to complete the switchover back to the operating position and the scram circuit was deprived of the true signal.
Questions may be directed to me at 515-294-6422.
Sincerely, 0-Wdbbh .
Richard A. Hendrickson Reactor Manager
/rpa Enclosure C: U. S. Nuclear Regulatory Commission Washington, D. C. 20555 h
Attn: Document Control Desk k\s gpggg S
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.JUN 191987.
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I Docket No: 50-116 Special Report Malfunction of a Safety Channel Test Switch Description of the Event During a normal startup of the Iowa State UTR-10 on June 3, 1987, the pre-critical tests of the high power scram circuit for each of the two redun-dant linear percent power channels were completely satisfactory. However, as reactor power was increased above 50%, the senior reactor operator noted one linear percent power channel was not indicating power icvel on the panel meter. (The scale on the analog meter indicating power for this channel is not graduated until 20%.) The SRO ordered the reactor shut down, and he initiated the investigation to discover the cause.
Cause of the Malfunction One essential task performed by the operate-test switch is the disconnec-tion of the true signal and substitution of the test signal when it is in the test position. While in the test position, the test switch logic prohibits normal operation until the switch is in the operate position.
There is no way to know that the true signal is available to the scram circuit, after completing the test, until the power level is high enough to be observed on the linear percent power meter.
After the reactor was shut down, the SRO performed the precritical high power scram test again, and it was successful. This showed that the panel meter was operable. The SRO, with the concurrence of the Reactor Manager, applied ordinary contact cleaner to the switch and observed normal opera-tion during subsequent reactor operation later the same day.
Conclusion:
When the test switch was returned to the operate position after the precritical test of the high power scram function, one of the many contacts of the switch did not make proper contact and the true signal was not available to the panel meter or the scram circuit.
Plan to Prevent Recurrence The design and construction of the safety channels are not questioned; they have given flawless service for almost 17 years.
Maintenance practice will be changed to include switch contact cleaning at the time of the annual calibration of the safety channels.