Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| ML20202F916 | 29 January 1998 | Special Rept:On 980128,two of Three Fire Protection Pumps Were Removed from Svc as Result of Sys Configuration Necessary to Support Planned Maintenance.Fire Pumps Were Returned to Svc on 980128 | |
| ML20138F580 | 29 April 1997 | Special Rept:On 970402,declared Reactor Bldg Wide Range Gas Monitor Inoperable.Caused by Ruptured Pump Diaphragm. Initiated Work Order,Installed Replacement Pump & Declared Pump Operable | |
| ML20137Y217 | 15 April 1997 | Special Rept:On 961220,util Rail Car Was Released to Burlington Northern Railroad from Monticello Nuclear Plant. Rail Car Was Delayed in Chicago as Result of Problems W/Bill of Lading on Computer Sys.Rail Car Was Delivered on 970131 | |
| ML20101E832 | 15 March 1996 | Special Rept:On 960314,two of Three Fire Pumps Removed from Svc for Planned Mod Work.Returned Both Fire Pumps to Svc Same Day | |
| ML20094E437 | 31 October 1995 | Special Rept:On 951010,sys Engineer & Technicians Reintiated Work on B Channel of Reactor Bldg Vent Radiation Monitor, After Providing Proper Notification to Main Control Room. Caused by Incorrect Channels Removed from Svc | |
| ML20082R660 | 19 April 1995 | Special Rept:On 950404,discovered That Manual Isolation Valves for 'A' Channel in Closed Position.Cause of Failure to Correctly Position Valves Will Be Assessed.Valves Placed in Required Position & Demonstrated Operability | |
| ML20082E566 | 6 April 1995 | Special Rept:On 950326,pump Discharge Relief Valve for Electric Screen Wash/Fire Pump Became Inoperable.Valve Had to Be Secured to Permit Installation of an Isolation Device. Pump Returned to Operational Status After Device Installed | |
| ML20080G473 | 1 February 1995 | Special Rept:On 950119,two of Three Fire Protection Pumps Out of Svc for Period of Approx 15 H.Action Taken for Planned Preventative Maint on Two Check Valves & Drain Valve in Fire Suppression Sys.Roving Fire Watch Established | Fire Watch |
| ML20067D135 | 23 February 1994 | Special Rept:On 940126,fire Door 105 Declared Inoperable Due to Inability to Close Properly.Caused by Higher than Normal Differential Pressure Between Plant Administration Bldg & Turbine Bldg.Cause of Failure Corrected | Fire Barrier Hourly Fire Watch |
| ML20117A580 | 24 November 1992 | Special Rept:On 921020,determined That RHR Sample Supply Loops a & B Excess Flow Check Valves Not Included in ASME Section XI Program.Caused by Lack of Proven Test Procedure. Valves Incorporated Into Third 10-yr ASME Program | |
| ML20082G926 | 15 August 1991 | Special Rept:On 910719,potential for Inoperable Penetration Fire Barrier Identified.Caused by Use of Less Conservative, But Technically Acceptable,Design Alternatives in Plant Const.Vents Will Be Rerouted | Fire Barrier Fire Watch Hourly Fire Watch |
| ML20244E594 | 16 June 1989 | Special Rept:On 890603,two Out of Three Diesel Fire Pumps Were Inoperable for Less than 12 H.Caused by Diesel Fire Pump Day Tank Outlet Valve Being Closed Instead of Fill Valve During Performance Test 1158.Test Revised | |
| ML20081G956 | 25 October 1983 | Ro:On 831024,trip Coil for Reactor Recirculation Motor Generator Set 11 Drive Breaker Failed to Trip Automatically. Investigation Ongoing.Trip Coil Replaced | |
| ML20066E013 | 1 November 1982 | Ro:On 821031,thru Wall Defect Found on C 12-inch Recirculation safe-end to Pipe Weld Joint.Resolution Under Investigation | |
| ML20064E514 | 21 October 1982 | Ro:On 821020,thru Wall Defect Found on E 12-inch Recirculation Sys Safe End to Pipe Weld Joint.Indications Will Be Documented as Revision to RO 82-16 Reported on 820928.Resolution Being Investigated | |
| ML20064E476 | 11 October 1982 | Ro:On 821009,linear Indications Confirmed to Exist on Three Addl Welds in Recirculation Sys.Indications Will Be Documented as Revision to RO 82-16 Reported on 820928. Resolution Being Investigated | |
| ML20071N436 | 28 September 1982 | Ro:On 820928,crack Indication in End Cap of a Recirculation Riser Confirmed by Radiography.Indications Initially Detected by Ultrasonic Exam During Normal Inservice Insp. Remedial Measures Under Investigation | |
| ML20071L826 | 16 September 1982 | Ro:On 820915,leak Discovered on Primary Containment Suppression Chamber Nitrogen Control Sys Inboard Isolation Valve (AO-2378).Leakage Less than Tech Spec Allowable Leakage | |
| ML20053E807 | 2 June 1982 | RO Iii:On 810224,failure of Discharge Valve on Instrument & Svc Air Compressor Resulted in Loss of Instrument Air Sys Pressure Causing Plant Scram.Failed Check Valve Replaced W/Similar Unit | Safe Shutdown Systematic Assessment of Licensee Performance |
| ML20058L343 | 31 July 1978 | Ro:On 780728,control Rod Drive 30-47 Delayed Approx 1.4 Before Scramming.Buna N Disk in Plunger Broken in Pieces.Plungers on 242 Scram Pilot Valves & Two Backup Scram Pilot Valves Removed & Replaced | |
| ML20090L831 | 2 June 1978 | Ro:On 780505,steam Leak Noted in RCIC Inlet Steam Line & Drain Line to Condenser.Caused by Pinhole Failure on Weld on 300 Lb Socket Weld.Hole Temporarily Patched | |
| ML20091A994 | 10 March 1978 | Ro:On 780309,smear Survey of Chem Nuclear Sys Inc Model 4-45 Shipping Cask Disclosed Max Surface Contamination of 25,900 Disintegrations Per Min Per 100 Square Centimeters.Cask Will Be Decontaminated | |
| ML20127G617 | 2 February 1978 | Advises That on 780202,during Surveillance Test,One Suppression Chamber to Drywell Vacuum Breaker Failed to Reclose Following Exercise.Plant Shutdown Initiated | |
| ML20086D514 | 6 January 1978 | Telecopy Ro:On 780105,discovered That One of Two Nuclear Engineering Co Model B3-1 Shipping Casks Provided w/1-inch Diameter Lid Bolts Rather than 1-1/4 Inch Size Specified in Certificate of Compliance 6058 | |
| ML20086D520 | 14 December 1977 | Telecopy Ro:Heating Steam Coil Leak in Reactor Bldg Ventilation Supply Unit V-AH-4A Resulted in Freezing of Condensate at Inlet to Unit & Subsequent Inoperability of Associated Secondary Containment Isolation Dampers | |
| ML20086D537 | 14 October 1977 | Telecopy Ro:Insp of Internal Torus Catwalk Support Structure Revealed That Catwalk Mitered Sections Not All Attached to Horizontal Catwalk Support Plates in Some Manner.Attachment Locations Will Be Upgraded | |
| ML20086D550 | 13 October 1977 | Telecopy Ro:On 771012,local Leak Rate Testing of MSIV AO-2-80A & Nitrogen Instrument Air Sys Isolation Valve CV-7436 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation | |
| ML20086D554 | 5 October 1977 | Telecopy Ro:On 771004,local Leak Rate Testing of HPCI Sys Discharge Isolation Check Valve HPCI-9 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation | |
| ML20086D557 | 29 September 1977 | Telecopy Ro:On 770929,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO-14-13A Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation | |
| ML20086D561 | 14 September 1977 | Telecopy Ro:On 770913,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO 14-13B Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Related Event on 770914 | |
| ML20086D567 | 12 September 1977 | Telecopy Ro:Main Steam Drain Isolation Valve MD 2373 & Main Steam Outboard Isolation Valve AO 2-86A Exceeded Tech Spec Acceptance Criteria for Local Leak Rate Tests | |
| ML20086D642 | 11 July 1977 | Telecopy Ro:On 770709,determined That Recombiner Sys a Offgas Flow Control Valve PCV 7489A Could Be Opened W/ Controlling Solenoid Valve Deenergized.Valve Held from Svc Pending Investigation | |
| ML20058K611 | 9 March 1977 | Ro:On 770223,discovered Withdrawal of in-sequence Control Rod Resulted in Period Less than 5-s & IRM Scram | |
| ML20086D691 | 2 March 1977 | Telecopy Ro:On 770301,torus Water Vol Found to Be Slightly Below Min Vol Established by Tech Specs.Water Vol Restored to Normal Operating Level | |
| ML20086D703 | 24 February 1977 | Telecopy Ro:On 770223,while Withdrawing in-sequence Control Rod to Bring Reactor Critical,Reactor Period of Less than 5 Obtained | |
| ML20086D788 | 10 September 1976 | Telecopy Ro:On 760909,discovered That Torus Water Vol Several Hundred Cubic Ft Below 68,000 Cubic Ft Min Required by Tech Specs.Caused by Failure to Correct for Vol Vs Level Correlation | |
| ML20056B854 | 21 May 1976 | Informs of 760520 Event Involving TIP Bell Valve Which Failed to Properly Close During Operation of TIP Sys.Valve Cleaned,Relubricated & Closure Spring Tension Increased | |
| ML20086D823 | 5 May 1976 | Telecopy Ro:On 760504,during Routine Surveillance Test, Primary Containment Oxygen Concentration Found to Be in Excess of Tech Spec Limit.Caused by Leakage from Drywell Instrument Air Sys Into Containment Nitrogen Supply Line | |
| ML20127L261 | 22 September 1975 | Informs of 750921 Incident Re Countrate Decreasing Below 3 Counts Per While Performing Refueling Core Alterations. Countrate Increased & Refueling Operations Recommenced. Further Investigation Continuing | |
| ML20127L275 | 22 September 1975 | Informs of 750920 Incident Re Drywell Equipment Drain Sump Isolation Valves AO 2561A & B Exceeding TS Acceptance Criteria.Further Investigation Continuing | |
| ML20127L255 | 19 September 1975 | Informs That on 750919,during Local Leak Rate Testing of MSIVs 2-86A & 2-88A,combined Leakage of Valves Exceeded Acceptance Criteria.Further Investigation Continuing | |
| ML20127L239 | 15 September 1975 | Informs of 750914 Incident Re Discovery That Hydraulic Shock Suppressor Located Inside Primary Containment on Loop B HPCI Line Inoperable Due to Loss of Oil.Reactor in Cold Shutdown for Refueling.Further Investigation Underway | |
| ML20127L174 | 21 August 1975 | Discusses 750818 Incident Re Broken Seal Cooling Line at Threaded Connection on Reactor Water Cleanup Pump 12.Pump Immediately Isolated & Line Repaired.Investigation Into Cause of Failure Continuing | |
| ML20127L265 | 28 July 1975 | Ro:On 750727,operator Motor Failed & Stalled Due to Stalled Rotor Current Overheating Windows.Investigation Pending | |
| ML20127L252 | 14 July 1975 | Ro:On 750713,small Leak Developed on Local Pressure Gauge Monitoring Reactor Pressure.Root Valve for Pressure Gauge Closed,Allowing Ref Leg to Refill & Water Level Indication to Return to Normal | |
| ML20058L176 | 11 July 1975 | Ro:On 750624 & 25,10 Initial Core Fuel Assemblies Which Had Been Identified as Leakers & Removed from Core at End of Cycles 2 & 3 Inspected Using Underwater Television | |
| ML20058K675 | 3 July 1975 | Notifies That on 750703,during Routine Surveillance Testing, Reactor High Pressure Scram Switches Found Inoperable | |
| ML20127B737 | 27 May 1975 | Ro:On 750525 Core Spray Sys Motor Operated Valve Failed to Reopen by Means of Motorized Operator.Valve Was Returned to Normal Open Position by Local Handwheel | |
| ML20058K695 | 5 May 1975 | Ro:On 750505,discovered That Control Circuit for Valve Steam Supply to RCIC Turbine Was Deenergized by Motor Control Unit Undervoltage Relay Coil Opening.Coil Replaced & Remote Operability of Valve Demonstrated | |
| ML20127L147 | 1 May 1975 | RO 75-12:on 750429,surveillance Test for Exercising Unit 2 Containment Vacuum Breaker Isolation Valve CV-31628 Showed Valve to Be Inoperable |