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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20077M2941991-08-0707 August 1991
Suppls Ro:On 910731,safety Sys Component Failed Due to Excessive Wear to Brass Gears.Limit Switch Will Be Added to Rack That Raises Rod & Rod Drop Surveillance Check Procedure & Daily pre-start Check Procedures Will Be Modified
ML20077K0991991-08-0101 August 1991
Ro:On 910731,control Rod Withdrew Beyond Upper Lattice Plate & Failed to Insert Upon Scram.Caused by Improper Alignment of Control Rod Position Indicator & Limit Switch Drive Train.Realigned Drive Train.No Damage to Equipment
1991-08-07
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Category:TEXT-SAFETY REPORT
MONTHYEARML18059A8751994-03-0303 March 1994
LER 94-003-00:on 940203,position Switches for Containment Air Cooler Svc Inlet & Valves Not Qualified for Submergence. Caused by Master Equipment List Which Did Not Alert User of Existence of Qualification restrictions.W/940303 Ltr
ML18059A6811994-02-10010 February 1994
LER 93-013-01:on 930427,loss of Onsite AC Power Due to Both Emergency Diesel Generator Simutanously Inoperable.Caused by Electrical Distribution Grid.Corrective Actions:Electrical Section revised.W/940210 Ltr
ML20077R6821991-08-0808 August 1991
Paper Entitled, State Point Experiments for Tight Lattice of 4.81 W/O Enriched UO2 Fuel Pins, to Be Presented at ANS Meeting in San Francisco,Ca
ML20077M2941991-08-0707 August 1991
Suppls Ro:On 910731,safety Sys Component Failed Due to Excessive Wear to Brass Gears.Limit Switch Will Be Added to Rack That Raises Rod & Rod Drop Surveillance Check Procedure & Daily pre-start Check Procedures Will Be Modified
ML20077K0991991-08-0101 August 1991
Ro:On 910731,control Rod Withdrew Beyond Upper Lattice Plate & Failed to Insert Upon Scram.Caused by Improper Alignment of Control Rod Position Indicator & Limit Switch Drive Train.Realigned Drive Train.No Damage to Equipment
ML20073P8361991-04-30030 April 1991
Abb Cenp Critical Experiments in Reactor Critical Facility of Rpi
ML20238A6361987-08-31031 August 1987
Safety Evaluation Supporting Amend 8 to License CX-22
ML20235N8331987-07-0707 July 1987
Safety Evaluation Supporting Conversion Order to Convert from High Enriched to Low Enriched U Fuel for License CX-22
ML20206Q5681987-04-30030 April 1987
Reactor Operator Requalification (Ror) Program for Rensselaer Polytechnic Inst Reactor Critical Facility (Rcf)
ML20212N3981987-03-0303 March 1987
Design Basis Transient Analyses for Low Power Research Reactors
ML20212N4021987-03-0303 March 1987
Difxy,Fortran Code for Solution of Multi-Energy Group Diffusion Equations in X-Y Geometry
ML20214R9901986-12-0101 December 1986
Safety Evaluation Supporting Amend 6 to License CX-22
ML20215C1671986-06-30030 June 1986
Critical Facility Safety Analysis Rept
ML20141F9481986-03-17017 March 1986
Annual Operating Rept for 850301-860301
ML20154R4901986-03-17017 March 1986
Annual Rept of Tests & Experiments for 850301-860301
ML20115B5321985-03-0101 March 1985
Annual Rept of Tests & Experiments,820301-830301
ML20115F6081985-03-0101 March 1985
Annual Operating rept,840301-850301
ML20087K4121984-03-0101 March 1984
Annual Operating Rept,Mar 1983 - Mar 1984
ML20072N1201983-03-0101 March 1983
Annual Operating Rept Mar 1982 - Mar 1983
ML20072F9891983-03-0101 March 1983
Submits Annual Rept of Tests & Experiments,Mar 1982 - Feb 1983
ML20087H0681983-02-28028 February 1983
Annual Rept of Tests & Experiments,Mar 1982 - Feb 1983
ML20070P1661983-01-21021 January 1983
Rensselaer Polytechnic Inst Critical Facility Sar
ML19350C4631981-02-14014 February 1981
Ro:During pre-startup Check,Moderator Dump Valve Solenoid Failed.Attempt to Energize Solenoid for Moderator Fill Unsuccessful.Cause Not Stated.Component Repaired & Reinstalled
1994-03-03
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s Rensselaer pennieni .4 Noticar F.ncinceiins & Engineering 11 row.
August 1,1991 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 On 31 July 1991 at 1:00 P.M. there was a Reportable Occurrence (Technical Specification 1.Q,4, .... safety system component failure....) at the RPI Reactor Critical Facility. (:ontrol rod 7 withdrew beyond the upper lattice plate and failed therefore to insert ,jpon scram. This control rod withdrew too far because of a failure of the Rod Out [mit switch to operate at the correct height of control rod withdrawal. This occurred )ccause of improper alignment of the control rod position indicator and limit swi'th drive train. The problem was corrected by realigning the drive train.
The othr control rod drive and indicator systems were immediately checked and ,
found to be satisfactory. There was no damage to equipment or people.
T. 'tragoun, Region 1, and T. Michaels, NRC 11Q, were notified within an hour afte the occurrence; this satisfied Tech. Spec. 6.5.2.a. In a return call at 3:00 P.M. of t same day T. Dragoun communicated the NRC permission to resume operation 4and this was done.
Sir :erely, y 4%s Dr. Donald R. Ilarris Director RPI Reactor Critical Facility (RCF)
DRH:Jjd' cc: Dr. R.C. Block, NSRil Chairman and NE&EP Dept. Head Dr. Gary Judd, Vice Provost, Academic Affairs Dr. A.E. Bergies, Dean, School of Engineering knw.n I,nancering center (SW 216tu e Qieritner IAunatory (LN ZE9M h
- l<ennelaer iblyteihnic Institute
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