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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML19350C4631981-02-14014 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
1981-02-14
[Table view]
Category:LER)
MONTHYEARML19350C4631981-02-14014 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
1981-02-14
[Table view]
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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Text
1 M
Deptrtm:nt of Nuct:ar Enginesring C.>h Rensselaer Polytechnic Institute Troy, New York 12181 4 February 14, 1981 Y Y
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2;v% 2Ggg"e
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iEb r i
Q s.k?J Director, Region I D
- he Nuclear Regulatory Comission King of Prussia, PA 19406 %, [g g .8 ,
Subject:
Safety system component failure at the RPI CEF (CX-22)
Daar Sir:
During a pre-startup check it was discovered that the Moderator Dump valve solenoid was failed. The normal attempt to energize the solenoid for Moderator fill was unsuccessful.
The solenoid positions a two position air valve to pneumatically hold the Moderator butterfly shut when the safety amplifier circuits are energized. A scram signal drops the Moderator level by deenergizing the solenoid. The system serves as a supplementary scram function since the control rod shutdown margin surpasses License specification.
NRC Region I headquarters was notified by telephone of the event.
There existed no question of safety significance since tne reactor was not operating and the coil failed in a manner which would cause a reactor shutdown.
The component has been repaired and reinstalled. Tests of the system were satisfactory.
The facility is in a normal operational mode.
Sincerely yours, l
. fi 0-?Yj 11/'
Peter R. Nelson '/
' Supervisor Critical Experiments Facility L.D. Walthousen Laboratory PRN:jm cc: D.R. Harris
_f 8104010824