ML19289F142
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| ML19289F142 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/01/1979 |
| From: | NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| LER-79-001, LER-79-1, NUDOCS 7906040322 | |
| Download: ML19289F142 (1) | |
Similar Documents at Prairie Island | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20024J2451994-10-0606 October 1994
[Table view]LER 94-006-00:on 940907,observed Receipt of Annunciator 12 Charging Pump Overload Trip.Caused by Overheated C Phase Loadside Connection at Mccb.Breaker Was Replaced & Tested. W/941006 Ltr ML20029E4701994-05-12012 May 1994 LER 94-001-00:on 940412,discovered That Total Pressure Offset Constant in Error.Caused by Technician Error. Procedure Will Be Revised to Prevent recurrence.W/940512 Ltr ML20029D7761994-05-0404 May 1994 LER 94-002-00:on 940303,noble Gas Monitor in R-35 Did Not Respond When source-checked During Surveillance.Caused by Component Failure.Corrective Actions:Monitor Repaired & Returned to svc.W/940504 Ltr ML20046C7791993-08-0505 August 1993 LER 93-009-00:on 930715,receipt of Annunciator Charging Pump 12 Overload Trip Observed by CR Operators,Resulting in Unplanned Closure of Containment Isolation Valve.Standby Charging Pump Started Immediately ML20046A9151993-07-26026 July 1993 LER 93-007-01:on 930413,discovered That Valves Required to Mitigate Consequences of Accident Not Included in Section XI ISI & Testing Program.On 930624,identified Six Addl Valve Inappropriately Ommitted from Subj Program.Valves Included ML20046A8931993-07-23023 July 1993 LER 93-008-00:on 930624,observed That Valve CV-31740, Instrument Air to Unit 1 Containment Closed Due to Failure of Coil in Solenoid Operated Pilot Valve.Valve Reopened Locally to Restore Instrument air.W/930723 Ltr ML20044D2181993-05-13013 May 1993 LER 93-002-00:on 930403,containment Isolation Valve Which Controls Reactor Makeup Water to Containment Exceeded Max Time for Closure.On 930413,lockwire & Safety Tag Removed. Caused by Communication Errors.Safety Tag Process Reviewed ML20044D2241993-05-13013 May 1993 LER 93-007-00:on 930413,discovered That Certain Feedwater Valves,Required to Mitigate Consequences of Accident,Not Included in ASME Section XI ISI & Test Program.Caused by Failure to Interpret Requirements.Valves Tested ML20024H2061991-05-23023 May 1991 LER 91-003-00:on 910423,auto-start Occurred of One Train of Auxiliary Bldg Special Ventilation Sys.Cause Unknown.Plant Mod Initiated Removing Unnecessary Wiring That Could Short Monitor module.W/910523 Ltr ML20024G7001991-04-22022 April 1991 LER 91-002-00:on 910323,auto-start of Control Room Special Ventilation Sys Occurred.Caused by Spike on Newly Installed Radiation Monitor.Wiring Changed to Provide Time Delay Feature for Remaining Four modules.W/910422 Ltr ML20028H8491991-01-28028 January 1991 LER 90-012-00:on 901229,control Room Operators Received Annunciation of Reactor Trip.Caused by Rod Control Sys Failures.Failed Cards in Rod Control Sys replaced.W/910128 Ltr ML20028H0461990-09-26026 September 1990 LER 89-018-03:on 891024,automatic Start of Auxiliary Bldg Ventilation Sys Occurred.Caused by Electronic Spike on Radiation Monitor.Radiation Monitor Modules Will Be Replaced by Upgraded Monitor module.W/900927 Ltr ML20043G1971990-06-15015 June 1990 LER 90-006-00:on 900517,electrical Spike on Radiation Monitor R-25 Caused auto-start of Spent Fuel Pool Special Ventilation Sys.Caused by Procedural Inadequacy.Request for Training Issued Re Basics of Procedure writing.W/900615 Ltr ML20043E0601990-06-0404 June 1990 LER 90-005-00:on 900504,control Room Received High Radiation Alarm & Indication of Automatic Start of Spent Fuel Pool Special Exhaust Fan 121 on Two Occasions.Caused by Electrical Spike on Monitor.Modules replaced.W/900604 Ltr ML20043B6041990-05-24024 May 1990 LER 90-004-00:on 900424,discovered That Surveillance Test SP1042, Resistance Temp Detector Bypass Flow Meter Functional Test Not Performed within Required Time Period. Caused by Personnel Error.Test performed.W/900524 Ltr ML20043E3761990-05-18018 May 1990 LER 90-007-00:on 900517,discovered That Several Relays Deenergized & Automatic Start & Loading of Diesel Generator D1 Initiated.Caused by Inadequate Design.Mod Initiated to Install Test points.W/900608 Ltr ML20042F5681990-05-0404 May 1990 LER 89-021-01:on 891212,chlorine Monitors on One Train of Control Room Ventilation Inoperable for More than 11 H. Caused by Personnel Error.Operating Procedure for Chlorine Monitoring Sys Issued & Training provided.W/900504 Ltr ML20042E6811990-04-23023 April 1990 LER 90-003-00:on 900323,automatic Start of Safeguards Cooling Water Pump Occurred Due to Inadequate Procedures. Plant Procedures Revised to Improve Guidance for Detecting Loss of prime.W/900423 Ltr ML20012D4941990-03-19019 March 1990 LER 89-004-01:on 891221,reactor Trips & Loss of Power to Reactor Coolant Pumps Occurred.Caused by Malfunctions in MG Sets,Rod Control Sys & Substation Breaker Control Sys. Voltage Regulator for MG Set replaced.W/900319 Ltr ML20006E8211990-02-20020 February 1990 LER 90-002-00:on 900117,review of Cooldown Data Showed That Cooldown Rate of Pressurizer Exceeded Tech Spec Limit.Caused by Procedure Inadequacy.Procedures Revised to Require Use of Water Space Temp to Find Cooldown rate.W/900220 Ltr ML20006E4581990-02-16016 February 1990 LER 90-001-00:on 900117,technician Mirror Contacted Bare Power Supply Terminal & Shorted Terminal to Ground,Causing Power Supply to Trip & Isolation of Outside Air to Control Room.Exposed Wire Terminal Points covered.W/900216 Ltr ML20006A9721990-01-22022 January 1990 LER 89-004-00:on 891221,unit Tripped & Reactor Coolant Pumps Lost Power.Caused by Faulty Voltage Regulation of One CRD Mechanism motor-generator Set.Regulator for Set Replaced & Tested.On 891226,identical Trip occurred.W/900122 Ltr ML20005G3731990-01-11011 January 1990 LER 89-021-00:on 891211,computer Alarmed Indicating Malfunction of Chlorine Monitors 121 & 122 & Leaving Control Room Ventilation Sys Inoperable for More than 11 H.Caused by Personnel Error.Monitor 122 Returned to normal.W/900111 Ltr ML19351A4681989-12-11011 December 1989 LER 89-020-00:on 891108,17,20,23,1201 & 08,automatic Isolation of Control Room Supply & Exhaust Occurred.Caused by Malfunctions of Chlorine Gas Detectors.Addl Monitors Installed & Actuation Logic modified.W/891211 Ltr ML20005D7071989-11-30030 November 1989 LER 89-018-01:on 891024,25,31 & 1112,control Room Received High Radiation Alarm Which Initiated Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Radiation Monitor Spikes.Monitor Modules replaced.W/891130 Ltr ML19332C6171989-11-22022 November 1989 LER 89-018-00:on 891024,25 & 1112,control Room Received Train a High Radiation Alarm,Initiating Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Spike of Radiation Monitor.Monitor replaced.W/891122 Ltr ML19332C6241989-11-22022 November 1989 LER 89-003-00:on 891023,measured Leakage Rate Exceeded Tech Specs Limit While Performing Surveillance Test Sp 2136. Caused by Wear of Grafoil Packing Due to High Frequency of Door Usage.Test Procedures modified.W/891122 Ltr ML19332C7001989-11-20020 November 1989 LER 89-019-00:on 891025,Train a of Auxiliary Bldg Special Ventilation Sys Started Automatically When Power Mistakenly Turned Off.Caused by Personnel Error.Involved Personnel Counseled.Clarifying Revs Made to procedure.W/891121 Ltr ML19325D4901989-10-16016 October 1989 LER 89-017-00:on 890914,discovered That Present Position of Transfer Switch for Power Supplying Control & Protection Relays for Diesel Generator Does Not Meet Requirements of App R.Caused by Inadequate procedures.W/891016 Ltr ML19325C7491989-10-10010 October 1989 LER 89-016-00:on 890908,control Room Received Train B High Radiation Alarm,Which Initiated Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Spike on Radiation Monitor 2R-30.Monitor Upgrade Being pursued.W/891010 Ltr ML19325C1991989-10-0505 October 1989 LER 89-015-00:on 890905 & 23,special Ventilation Sys of Control Rooms 122 & 121 Actuated Automatically.Caused by False High Chlorine Signal & Broken Chlorine Sensitive Paper Tape,Respectively.Detectors repaired.W/891005 Ltr ML19325C1981989-10-0505 October 1989 LER 89-014-00:on 890905,operations Personnel Recalled That SP1093.1 Performed Two Wks Previously Instead of SP1093.2. Caused by Personnel Error in Selecting Incorrect Procedure. Proper Notifications Made & SP1093.2 performed.W/891005 Ltr ML20028E3301983-01-12012 January 1983 LER 82-029/01T-0:on 821228,tiny through-wall Crack Found in heat-affected Zone of Weld on Safety Injection Supply Line from Boric Acid Storage Tanks.Cause Unknown. Fracture Mechanics Analysis Underway ML20028C2441982-12-30030 December 1982 LER 82-025/03L-0:on 821130,one Steam Flow Channel Differed from Redundant Channels During Power Reduction Due to out- of-calibr Transmitter.Cause Not Known.Transmitter Recalibr & Returned to Svc.Transmitter to Be Replaced If Drift Recurs ML20028C3681982-12-30030 December 1982 Signed LER 82-025/03L-0:on 821130,during Power Reduction,One Steam Flow Channel Differed from Redundant Channels. Transmitter Showed Out of Calibr.Cause Unknown.Transmitter Recalibr.Bistables Placed in Trip During Recalibr ML20028C1651982-12-22022 December 1982 LER 82-024/03L-0:on 821123,diesel Generator D1 Inoperable for Approx 4 Minutes After Lockout of Engine Shutdown Circuit Occurred.Probably Caused by Sticky Action of Speed Switch.Further Exam of Circuitry Will Be Performed ML20028A9761982-11-17017 November 1982 LER 82-021/03L-0:on 821027,following Use in Routine Sampling Procedure SV-33655,hot Leg Loop B Sample Inside Containment Isolation Valve Failed to Remain Closed.Caused by Malfunction of Limit Switch.Switch Replaced ML20051A9561982-05-0707 May 1982 LER 82-006/01T-0:on 820423,during Surveillance Test Sp 1104, Measured Reactor Coolant Boron Concentration Higher than Originally Predicted Value.Caused by Miscalculation of Predicted Worth.Analysis Performed to Monitor Disagreement ML20052B2731982-04-21021 April 1982 LER 82-005/03L-0:on 820322,review of Chemistry Logs Showed That Boric Acid Tank 11 Had Not Been Sampled.Caused by Communication Breakdown.Tank Sampled & Involved Personnel Will Review Rept ML20050A8331982-03-24024 March 1982 LER 82-004/03L-0:on 820226,maint Workman Accidentally Bumped Overspeed Trip Mechanism on Auxiliary Feedwater Pump, Tripping Valve & Making Pump Inoperable.Caused by Personnel Error.Valve Operator Reset ML20042A5101982-03-12012 March 1982 LER 82-003/03L-0:on 820209,during Annual Visual Insp,One Steam Exclusion Control Damper Found Inoperable.Caused by Failure of Drive Gear in Pacific Air Products Damper Model R-35-FS.Gear Replaced ML20049H6061982-02-24024 February 1982 LER 82-001/03L-0:on 820125,one Overpower Delta T Summing Unit Found Out of Spec.Caused by Foxboro Model 66RC-OL Summing Unit Instrument Drift.Device Recalibr.Evaluation Underway ML20049H6841982-02-24024 February 1982 LER 82-002/03L-0:on 820125,one Overpower Delta T Summing Unit Found Out of Spec High.Caused by Instrument Drift. Device Recalibr ML20041B4041982-02-12012 February 1982 Updated LER 81-030/03L-0:on 811211,during Testing,Degraded Voltage Relay 27A1/B25 Found W/Voltage Setpoint Outside Allowable Band.Exact Cause Unknown.Relays Recalibr & Found to Operate Correctly ML20041B3991982-02-12012 February 1982 Updated LER 81-029/03L-0:on 811210,during Surveillance Test of Bus 16 Undervoltage Relays,Error in Disconnecting Test Equipment Resulted in Blown Fuse for A-phase Relays.Fuses Replaced & Normal Power Restored to Bus ML20040A5841982-01-15015 January 1982 LER 81-029/03L-0:on 811210,during Testing of Bus 16 Undervoltage Relays,Error in Disconnecting Test Equipment Resulted in Blown Fuse for a Phase Relays.Fuses Replaced. Undervoltage Relay Tests Will Be Revised ML20040A5671982-01-15015 January 1982 LER 81-030/03L-0:on 811210,degraded Voltage Relay 27A1/B25 Found W/Voltage Setpoint Outside Allowable Band.Causes Being Considered Are Last Calibr Error & Unfamiliarity W/Time Delay Relay Characteristics ML20039E5521981-12-30030 December 1981 LER 81-031/01T-0:on 811216,during Transfer of Spent Fuel in Preparation for Reracking of Pool 2,spent Fuel Assembly Top Nozzle Separated,Causing Assembly to Tip Toward Edge of Pool.Cause Unknown.Fuel Handling Operations Suspended ML20039C2751981-12-18018 December 1981 LER 81-028/03L-0:on 811118 & 1218,bistables 2-PC-431 G & I Found Out of Tolerance.Caused by Defective Potentiometer on 811118.On 811218,leads Were Tightened,Correcting Problem ML20039C2681981-12-16016 December 1981 LER 81-027/03L-0:on 811116,discovered That Pre,Absolute & Charcoal Filter Test Not Done on 11 Shield Bldg Ventilation Sys Replacement on 811112.Caused by Procedural Inadequacies & Poor Communications 1994-05-04 Category:RO) MONTHYEARML20024J2451994-10-0606 October 1994
[Table view]LER 94-006-00:on 940907,observed Receipt of Annunciator 12 Charging Pump Overload Trip.Caused by Overheated C Phase Loadside Connection at Mccb.Breaker Was Replaced & Tested. W/941006 Ltr ML20029E4701994-05-12012 May 1994 LER 94-001-00:on 940412,discovered That Total Pressure Offset Constant in Error.Caused by Technician Error. Procedure Will Be Revised to Prevent recurrence.W/940512 Ltr ML20029D7761994-05-0404 May 1994 LER 94-002-00:on 940303,noble Gas Monitor in R-35 Did Not Respond When source-checked During Surveillance.Caused by Component Failure.Corrective Actions:Monitor Repaired & Returned to svc.W/940504 Ltr ML20046C7791993-08-0505 August 1993 LER 93-009-00:on 930715,receipt of Annunciator Charging Pump 12 Overload Trip Observed by CR Operators,Resulting in Unplanned Closure of Containment Isolation Valve.Standby Charging Pump Started Immediately ML20046A9151993-07-26026 July 1993 LER 93-007-01:on 930413,discovered That Valves Required to Mitigate Consequences of Accident Not Included in Section XI ISI & Testing Program.On 930624,identified Six Addl Valve Inappropriately Ommitted from Subj Program.Valves Included ML20046A8931993-07-23023 July 1993 LER 93-008-00:on 930624,observed That Valve CV-31740, Instrument Air to Unit 1 Containment Closed Due to Failure of Coil in Solenoid Operated Pilot Valve.Valve Reopened Locally to Restore Instrument air.W/930723 Ltr ML20044D2181993-05-13013 May 1993 LER 93-002-00:on 930403,containment Isolation Valve Which Controls Reactor Makeup Water to Containment Exceeded Max Time for Closure.On 930413,lockwire & Safety Tag Removed. Caused by Communication Errors.Safety Tag Process Reviewed ML20044D2241993-05-13013 May 1993 LER 93-007-00:on 930413,discovered That Certain Feedwater Valves,Required to Mitigate Consequences of Accident,Not Included in ASME Section XI ISI & Test Program.Caused by Failure to Interpret Requirements.Valves Tested ML20024H2061991-05-23023 May 1991 LER 91-003-00:on 910423,auto-start Occurred of One Train of Auxiliary Bldg Special Ventilation Sys.Cause Unknown.Plant Mod Initiated Removing Unnecessary Wiring That Could Short Monitor module.W/910523 Ltr ML20024G7001991-04-22022 April 1991 LER 91-002-00:on 910323,auto-start of Control Room Special Ventilation Sys Occurred.Caused by Spike on Newly Installed Radiation Monitor.Wiring Changed to Provide Time Delay Feature for Remaining Four modules.W/910422 Ltr ML20028H8491991-01-28028 January 1991 LER 90-012-00:on 901229,control Room Operators Received Annunciation of Reactor Trip.Caused by Rod Control Sys Failures.Failed Cards in Rod Control Sys replaced.W/910128 Ltr ML20028H0461990-09-26026 September 1990 LER 89-018-03:on 891024,automatic Start of Auxiliary Bldg Ventilation Sys Occurred.Caused by Electronic Spike on Radiation Monitor.Radiation Monitor Modules Will Be Replaced by Upgraded Monitor module.W/900927 Ltr ML20043G1971990-06-15015 June 1990 LER 90-006-00:on 900517,electrical Spike on Radiation Monitor R-25 Caused auto-start of Spent Fuel Pool Special Ventilation Sys.Caused by Procedural Inadequacy.Request for Training Issued Re Basics of Procedure writing.W/900615 Ltr ML20043E0601990-06-0404 June 1990 LER 90-005-00:on 900504,control Room Received High Radiation Alarm & Indication of Automatic Start of Spent Fuel Pool Special Exhaust Fan 121 on Two Occasions.Caused by Electrical Spike on Monitor.Modules replaced.W/900604 Ltr ML20043B6041990-05-24024 May 1990 LER 90-004-00:on 900424,discovered That Surveillance Test SP1042, Resistance Temp Detector Bypass Flow Meter Functional Test Not Performed within Required Time Period. Caused by Personnel Error.Test performed.W/900524 Ltr ML20043E3761990-05-18018 May 1990 LER 90-007-00:on 900517,discovered That Several Relays Deenergized & Automatic Start & Loading of Diesel Generator D1 Initiated.Caused by Inadequate Design.Mod Initiated to Install Test points.W/900608 Ltr ML20042F5681990-05-0404 May 1990 LER 89-021-01:on 891212,chlorine Monitors on One Train of Control Room Ventilation Inoperable for More than 11 H. Caused by Personnel Error.Operating Procedure for Chlorine Monitoring Sys Issued & Training provided.W/900504 Ltr ML20042E6811990-04-23023 April 1990 LER 90-003-00:on 900323,automatic Start of Safeguards Cooling Water Pump Occurred Due to Inadequate Procedures. Plant Procedures Revised to Improve Guidance for Detecting Loss of prime.W/900423 Ltr ML20012D4941990-03-19019 March 1990 LER 89-004-01:on 891221,reactor Trips & Loss of Power to Reactor Coolant Pumps Occurred.Caused by Malfunctions in MG Sets,Rod Control Sys & Substation Breaker Control Sys. Voltage Regulator for MG Set replaced.W/900319 Ltr ML20006E8211990-02-20020 February 1990 LER 90-002-00:on 900117,review of Cooldown Data Showed That Cooldown Rate of Pressurizer Exceeded Tech Spec Limit.Caused by Procedure Inadequacy.Procedures Revised to Require Use of Water Space Temp to Find Cooldown rate.W/900220 Ltr ML20006E4581990-02-16016 February 1990 LER 90-001-00:on 900117,technician Mirror Contacted Bare Power Supply Terminal & Shorted Terminal to Ground,Causing Power Supply to Trip & Isolation of Outside Air to Control Room.Exposed Wire Terminal Points covered.W/900216 Ltr ML20006A9721990-01-22022 January 1990 LER 89-004-00:on 891221,unit Tripped & Reactor Coolant Pumps Lost Power.Caused by Faulty Voltage Regulation of One CRD Mechanism motor-generator Set.Regulator for Set Replaced & Tested.On 891226,identical Trip occurred.W/900122 Ltr ML20005G3731990-01-11011 January 1990 LER 89-021-00:on 891211,computer Alarmed Indicating Malfunction of Chlorine Monitors 121 & 122 & Leaving Control Room Ventilation Sys Inoperable for More than 11 H.Caused by Personnel Error.Monitor 122 Returned to normal.W/900111 Ltr ML19351A4681989-12-11011 December 1989 LER 89-020-00:on 891108,17,20,23,1201 & 08,automatic Isolation of Control Room Supply & Exhaust Occurred.Caused by Malfunctions of Chlorine Gas Detectors.Addl Monitors Installed & Actuation Logic modified.W/891211 Ltr ML20005D7071989-11-30030 November 1989 LER 89-018-01:on 891024,25,31 & 1112,control Room Received High Radiation Alarm Which Initiated Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Radiation Monitor Spikes.Monitor Modules replaced.W/891130 Ltr ML19332C6171989-11-22022 November 1989 LER 89-018-00:on 891024,25 & 1112,control Room Received Train a High Radiation Alarm,Initiating Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Spike of Radiation Monitor.Monitor replaced.W/891122 Ltr ML19332C6241989-11-22022 November 1989 LER 89-003-00:on 891023,measured Leakage Rate Exceeded Tech Specs Limit While Performing Surveillance Test Sp 2136. Caused by Wear of Grafoil Packing Due to High Frequency of Door Usage.Test Procedures modified.W/891122 Ltr ML19332C7001989-11-20020 November 1989 LER 89-019-00:on 891025,Train a of Auxiliary Bldg Special Ventilation Sys Started Automatically When Power Mistakenly Turned Off.Caused by Personnel Error.Involved Personnel Counseled.Clarifying Revs Made to procedure.W/891121 Ltr ML19325D4901989-10-16016 October 1989 LER 89-017-00:on 890914,discovered That Present Position of Transfer Switch for Power Supplying Control & Protection Relays for Diesel Generator Does Not Meet Requirements of App R.Caused by Inadequate procedures.W/891016 Ltr ML19325C7491989-10-10010 October 1989 LER 89-016-00:on 890908,control Room Received Train B High Radiation Alarm,Which Initiated Automatic Start of Auxiliary Bldg Special Ventilation Sys.Caused by Spike on Radiation Monitor 2R-30.Monitor Upgrade Being pursued.W/891010 Ltr ML19325C1991989-10-0505 October 1989 LER 89-015-00:on 890905 & 23,special Ventilation Sys of Control Rooms 122 & 121 Actuated Automatically.Caused by False High Chlorine Signal & Broken Chlorine Sensitive Paper Tape,Respectively.Detectors repaired.W/891005 Ltr ML19325C1981989-10-0505 October 1989 LER 89-014-00:on 890905,operations Personnel Recalled That SP1093.1 Performed Two Wks Previously Instead of SP1093.2. Caused by Personnel Error in Selecting Incorrect Procedure. Proper Notifications Made & SP1093.2 performed.W/891005 Ltr ML20028E3301983-01-12012 January 1983 LER 82-029/01T-0:on 821228,tiny through-wall Crack Found in heat-affected Zone of Weld on Safety Injection Supply Line from Boric Acid Storage Tanks.Cause Unknown. Fracture Mechanics Analysis Underway ML20028C2441982-12-30030 December 1982 LER 82-025/03L-0:on 821130,one Steam Flow Channel Differed from Redundant Channels During Power Reduction Due to out- of-calibr Transmitter.Cause Not Known.Transmitter Recalibr & Returned to Svc.Transmitter to Be Replaced If Drift Recurs ML20028C3681982-12-30030 December 1982 Signed LER 82-025/03L-0:on 821130,during Power Reduction,One Steam Flow Channel Differed from Redundant Channels. Transmitter Showed Out of Calibr.Cause Unknown.Transmitter Recalibr.Bistables Placed in Trip During Recalibr ML20028C1651982-12-22022 December 1982 LER 82-024/03L-0:on 821123,diesel Generator D1 Inoperable for Approx 4 Minutes After Lockout of Engine Shutdown Circuit Occurred.Probably Caused by Sticky Action of Speed Switch.Further Exam of Circuitry Will Be Performed ML20028A9761982-11-17017 November 1982 LER 82-021/03L-0:on 821027,following Use in Routine Sampling Procedure SV-33655,hot Leg Loop B Sample Inside Containment Isolation Valve Failed to Remain Closed.Caused by Malfunction of Limit Switch.Switch Replaced ML20051A9561982-05-0707 May 1982 LER 82-006/01T-0:on 820423,during Surveillance Test Sp 1104, Measured Reactor Coolant Boron Concentration Higher than Originally Predicted Value.Caused by Miscalculation of Predicted Worth.Analysis Performed to Monitor Disagreement ML20052B2731982-04-21021 April 1982 LER 82-005/03L-0:on 820322,review of Chemistry Logs Showed That Boric Acid Tank 11 Had Not Been Sampled.Caused by Communication Breakdown.Tank Sampled & Involved Personnel Will Review Rept ML20050A8331982-03-24024 March 1982 LER 82-004/03L-0:on 820226,maint Workman Accidentally Bumped Overspeed Trip Mechanism on Auxiliary Feedwater Pump, Tripping Valve & Making Pump Inoperable.Caused by Personnel Error.Valve Operator Reset ML20042A5101982-03-12012 March 1982 LER 82-003/03L-0:on 820209,during Annual Visual Insp,One Steam Exclusion Control Damper Found Inoperable.Caused by Failure of Drive Gear in Pacific Air Products Damper Model R-35-FS.Gear Replaced ML20049H6061982-02-24024 February 1982 LER 82-001/03L-0:on 820125,one Overpower Delta T Summing Unit Found Out of Spec.Caused by Foxboro Model 66RC-OL Summing Unit Instrument Drift.Device Recalibr.Evaluation Underway ML20049H6841982-02-24024 February 1982 LER 82-002/03L-0:on 820125,one Overpower Delta T Summing Unit Found Out of Spec High.Caused by Instrument Drift. Device Recalibr ML20041B4041982-02-12012 February 1982 Updated LER 81-030/03L-0:on 811211,during Testing,Degraded Voltage Relay 27A1/B25 Found W/Voltage Setpoint Outside Allowable Band.Exact Cause Unknown.Relays Recalibr & Found to Operate Correctly ML20041B3991982-02-12012 February 1982 Updated LER 81-029/03L-0:on 811210,during Surveillance Test of Bus 16 Undervoltage Relays,Error in Disconnecting Test Equipment Resulted in Blown Fuse for A-phase Relays.Fuses Replaced & Normal Power Restored to Bus ML20040A5841982-01-15015 January 1982 LER 81-029/03L-0:on 811210,during Testing of Bus 16 Undervoltage Relays,Error in Disconnecting Test Equipment Resulted in Blown Fuse for a Phase Relays.Fuses Replaced. Undervoltage Relay Tests Will Be Revised ML20040A5671982-01-15015 January 1982 LER 81-030/03L-0:on 811210,degraded Voltage Relay 27A1/B25 Found W/Voltage Setpoint Outside Allowable Band.Causes Being Considered Are Last Calibr Error & Unfamiliarity W/Time Delay Relay Characteristics ML20039E5521981-12-30030 December 1981 LER 81-031/01T-0:on 811216,during Transfer of Spent Fuel in Preparation for Reracking of Pool 2,spent Fuel Assembly Top Nozzle Separated,Causing Assembly to Tip Toward Edge of Pool.Cause Unknown.Fuel Handling Operations Suspended ML20039C2751981-12-18018 December 1981 LER 81-028/03L-0:on 811118 & 1218,bistables 2-PC-431 G & I Found Out of Tolerance.Caused by Defective Potentiometer on 811118.On 811218,leads Were Tightened,Correcting Problem ML20039C2681981-12-16016 December 1981 LER 81-027/03L-0:on 811116,discovered That Pre,Absolute & Charcoal Filter Test Not Done on 11 Shield Bldg Ventilation Sys Replacement on 811112.Caused by Procedural Inadequacies & Poor Communications 1994-05-04 Category:TEXT-SAFETY REPORT MONTHYEARML20217G4461999-09-30030 September 1999
[Table view]Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 ML20207J6951999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant ML20202J7711999-02-0404 February 1999 Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept ML20202G3761999-01-31031 January 1999 Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With ML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator ML20153B0761998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With ML20237A3961998-08-11011 August 1998 Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20236X8531998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant ML20236R6481998-07-15015 July 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept ML20236R0771998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant ML20249A5751998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) ML20247G2921998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20216C6361998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2 ML20216H0341998-03-31031 March 1998 Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept ML20217D2041998-03-13013 March 1998 Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn ML20236P9801998-03-12012 March 1998 Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys ML20248L3931998-03-10010 March 1998 ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept 1999-09-30 |
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