ML20054E193
| ML20054E193 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/16/1981 |
| From: | Murray T TOLEDO EDISON CO. |
| To: | Mcgregor L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20054E178 | List: |
| References | |
| NUDOCS 8204260240 | |
| Download: ML20054E193 (1) | |
Similar Documents at Davis Besse | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20042D8401990-03-30030 March 1990
[Table view]Supplement to 900105 Special Rept Re Inoperability of Diesel Fire Pump Due to Failure in Right Angle Gear Drive. Broken Studs Replaced W/Cap Screws Per Vendor Recommendations & Preventive Maint Activity Added ML20012C6861990-03-15015 March 1990 Ro:On 900204,daily Functional Test Not Done for Portable Fire Detection Sys.Caused by Shift Supervisor Failure to Ensure That Test Was Done.Requirements of Daily Functional Test Will Be Added to Operations Dept Monthly Activity Log ML20005F4401990-01-0505 January 1990 Special Rept:On 891129,diesel Fire Pump Failed While Providing Water to Support Cleaning Activity Unrelated to Fire Protection Sys.Caused by Broken Studs.Broken Studs Replaced W/Cap Screws Per Vendor Current Recommendation ML20050A9651982-03-22022 March 1982 RO NP-09-82-02:on 820222,free Chlorine Discharged in Excess of Ets,Section 2.3.1 Limit of 2-h Per Day.Caused by Equipment Deficiency.Feed Rate Will Be Verified During Chlorination Sys Lineup Changes ML20040G1191982-02-0303 February 1982 RO NP-09-82-01:on 820104,max Discharge Temp Above Ambient Lake Temp Limit Was Exceeded During Unusual Weather Change. Alarm T189 Setpoint Changed from 15 F to 17 F ML20010G3071981-08-31031 August 1981 Ro:Ie Bulletin 80-11 Analysis Determined That Listed Walls Would Be Overstressed During Seismic Event ML20005B3831981-06-25025 June 1981 RO NP-09-81-01:on 810526,max Discharge Temp Differential, Above Ambient Lake Temp,Was Slightly Exceeded.Caused by Difficulty in Maintaining Balance Between Operating to Prevent Exceeding Limit & to Prevent Cooling Tower Damage ML19350C2261981-03-17017 March 1981 Corrected Page 3 to Supplemental Info for LER 80-090 ML19341C2391981-02-18018 February 1981 Forwards Revised Supplemental Info Sheets for LER 79-050 Re Unplanned Reactivity Insertion.Caused by Mechanical, Personnel & Procedural Error.Valve Mu 39 Disassembled & Gaskets Installed ML19340C8281980-12-0101 December 1980 Supplemental Info Re RO NP-32-80-12:on 800724,w/unit in Mode 5,loss of Decay Heat Flow Observed.No Indication for Valve Position of Decay Heat Isolation Valve DH12.Revision Replaces Supplemental Info for RO 80-058 ML19345A8461980-11-18018 November 1980 Ro:On 801117 All Four Containment Pressure Transmitters Found to Be Inoperable Due to Surveillance Test Procedure Error.Emergency Tech Spec Relief Requested ML19337B4281980-09-0909 September 1980 RO NP-09-80-01:on 800116 & 0210,discharge Temp for Liquid Effluents Exceeded 20 F Above Lake Temp Due to Procedural Deficiencies.Cooling Tower Was Operated in Bypass Mode Causing Temp to Elevate Above Normal Temp During Startup ML19331B9031980-08-0404 August 1980 Ro:On 800803,heat Decay Flow Interrupted.Caused by Traveling Decay Heat Isolation Valve DH11 During Safety Features Actuation Sys Removal.Bistable Reinstalled & Pump Restarted within 3 Minutes ML19331B9001980-07-26026 July 1980 Ro:On 800724,decay Heat Flow Interrupted Twice.Caused by Inadvertently Shorted Decay Heat Isolation Valve DH12 Fuse Clip to Ground & by Tripped Output Bistable BA413 During Facility Change Request Work ML19320B9921980-06-27027 June 1980 Ro:On 800627,pipe Support HCB-40-41 on Component Cooling Water Supply to Control Rod Drive Mechanism Found Not Installed.Also,Lateral Restraint CCA-8-H15 on Pressurizer Relief Inlet Located 9 Inches from Analyzed Location ML19312E1641980-05-23023 May 1980 Ro:On 800430,chemistry & Health Physics Individual Received Dose of 4.7 Rems.Cause of Exposure Was Erroneously Low Reading on Meter or Misreading of Teletector.Individual Was Removed from Working in Radiation Controlled Areas ML19309G7341980-04-19019 April 1980 Ro:On 800418,discovered That Level of RCS Had Dropped Significantly.Control Room Operator Tripped Running Decay Heat Pump Because of Concern for Possible Loss of Suction. Caused by Vent Valve in Decay Heat Sys ML19305C9651980-04-0202 April 1980 NP-11-80-01,describing 791022 Beach Well Sample Which Indicated Tritium Concentration Three Times Beyond Normal. Procedure Changed to Require Monthly Rather than Quarterly Sampling ML19294B5191980-02-15015 February 1980 Ro:Reanalysis of RCS Pipe Restraints Revealed Less Conservative Design than Assumed on Two Reactor Coolant Hot Leg Whip Restraints Near Steam Generator Tops.Cause Unstated.Action During Refueling Outage in Eight Wks ML19296A9261980-02-12012 February 1980 RO-NP-09-80-01:on 800116,during Normal Plant Startup,Temp Differential Limit Between Station Liquid Effluent Discharge & Lake Temp Was Exceeded.Caused by Operation of Plant W/ Cooling Tower in Bypass Mode ML19276H5511979-11-13013 November 1979 Ro:On 791112,during Seismic Supports Analysis,Safety Factors on 11 Seismic Supports Found Lower than Expected.Unit Was in Cold Shutdown.Caused by Design Error in Initial Stress Calculations.Hangers Will Be Modified ML19210D7031979-11-12012 November 1979 Ro:On 791109,steam & Feedwater Rupture Control Sys Steam Generator Low Level Trip Setpoint Discovered Less Conservative than Tech Spec Requirements.Caused by Level Transmitter Setpoint Drift.Design Work Underway ML19254F9261979-11-0202 November 1979 RO-NP-09-79-06:on 791008,station Vent Recorder UJR5023 Was Inoperable.Caused by Recorder Not Advancing Paper Under Printer Due to Drive Shaft & Gear Mechanism Jam.All Ujr Recorders Will Be Replaced ML19275A5911979-09-27027 September 1979 RO NP-09-79-05:on 790831,during Review of Station Vent Data, Physicist Determined That Vent Recorder Was Inoperable. Caused by Inoperable Computer Point.Recorder Recalibr & Computer Input Card Changed ML19253A0961979-06-29029 June 1979 Notification of Violation of Tech Spec 3.4.1 on 790628. During Surveillance Testing on Reactor Protection Sys Channel 4,instrument & Control Technician Shorted Several Terminals W/Allegator Clip ML19282B7051979-02-28028 February 1979 Ro:On 790228,during Maint,Startup Transformer 01 Was de- Energized,But Addl Surveillance Required by Action Statement of Tech Spec 3.8.1.1 Was Not Performed.Caused by Personnel Oversight.Surveillance Testing Begun Approx 2-h Later ML19282A8681979-02-21021 February 1979 RO NP-09-79-04:on 790126,station Vent Monitor Re 2024 Generated Excessive Noise;Later Pump for Station Vent Monitor Re 2025 Seized.Caused by Normal Vane Wear & Low Flow During Testing.Pumps for Both Monitors Replaced ML19269C5951979-02-0101 February 1979 RO NP-09-79-02:on 790104,svc Water Sys Header Outflow Radiation Monitor Re 8432 Found Inoperable.Caused by Design Error Resulting in Component Deficiency.Flow Switch on Re 8432 Replaced & Facility Change Request Prepared ML19256A8011979-01-12012 January 1979 Reportable Occurrence NP-09-78-01:on 781215,during Routine Review of Shift Foreman'S Log,Discovered Svc Water Sys Out Header Radiation Monitor RE8432 Had Been Inoperable.Caused Apparently by Design Error.Facility Change Request Prepared ML19289C3681979-01-0505 January 1979 Reportable Occurrence NP-09-78-03 on 781209-10:discharge Temp for Station Liquid Effluents Exceeded 20 F Limit Above Lake Temp.Caused in Part by Design Deficiency in Sys Used to Determine Effluent Liquid Discharge Temp ML19256A7861979-01-0202 January 1979 to Suppl Info Sheet for LER NP-33-78-120 on 781005.Other Svc Water Valves Associated W/Component Cooling Water Heat Exchangers Were Inspected for Similar Inoperable Conditions.No Problems Noted ML19261B2121979-01-0202 January 1979 RO NP-09-79-01:on 790102,station Ventilation Radiation Monitors Re 2024 & Re 2025 Found Inoperable.Apparently Caused by Component Failure.Previous Occurrences on 770829 & 771214 Not Reported Due to Personnel Error.Units Repaired ML19263C1761978-12-15015 December 1978 RO-NP-09-78-01 on 781215:svc Water Sys Out Header Radiation Monitor Was Inoperable.Caused by Component Failure Due to Design Error.Personnel Informed of Environ Tech Specs ML20027A3751978-09-22022 September 1978 RO NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped Removing One of Two Reactor Coolant Pumps of Loop from Operation.B&C Phase Surge Capacitors Were Discovered to Be Damaged Due to Design Deficiency ML19329B0351978-07-18018 July 1978 RO 78-072-04-T-0:on 780710,station Effluent Chlorine Concentration Exceeded Tech Spec Limits.Caused by Personnel Mistakenly Returning Intake Chlorinator to Automatic Return to Svc to Be Expedited ML19317F5311978-04-17017 April 1978 Ro:On 780414,taped Electrical Terminations on Containment Air Cooler Units Found Not to Have Required LOCA Qualification.Caused by Mfg Inadequacy.Terminations to Be Reworked W/Qualified Tubing ML19317F5621978-02-24024 February 1978 Ro:On 780221,control Rod Drive Sys Trip Circuit Breaker Cabinets Found to Have Inadequate Welds.Welds to Be Lengthened to Conform W/Shaker Table Test During Apr 1978 Outage ML19317F5381977-11-16016 November 1977 Ro:On 771110,defect Discovered in Auxiliary Feed Pump Turbine Installed at Facility.Involves Potential for Governing Valve to Close While Turbine Not in Svc.Closure Caused by Excessive Vibration of Adjacent Startup Feed Pump ML19329A7821977-10-12012 October 1977 RO NP-33-77-73:on 770917,makeup Pump 1-2 Removed from Svc to Allow Repair of Oil Leak on Outboard Bearing Plate. Caused by Design Deficiency in End Plate Seal.New O-ring Installed ML19317F5351977-10-11011 October 1977 Ro:On 770930,defect Discovered in Governor on Auxiliary Feed Pumps Installed at Facility.Potential Created for Failure of Both Auxiliary Feed Pumps to Come Up to Design Speed Upon Startup.Superceded Util 771005 Ltr ML19329A8121977-10-0404 October 1977 RO NP-33-77-76:on 770901,reactor Coolant Pump 1-2-1 Tripped.Caused by Low Seal Injection & Component Cooling Water Flow,Due to Personnel Error.Instrument Air Valves Relabeled ML19329A7961977-10-0404 October 1977 RO NP-33-77-74:on 770907,decay Heat Suction Valve DH-12 Closed During Switching from Normal to Alternate Power Supply for Valve.Caused by Design Deficiency in Interlock/Control Circuit.Wiring Change in Process ML19329A8071977-09-28028 September 1977 RO NP-33-77-75:on 770829,RCS Have Less than 525 F in Mode 2,startup.Caused by Procedure Error in Shutdown Procedure & Fact That Only Three Reactor Coolant Pumps Were in Operation.Reactor Shut Down ML19319B8221977-09-27027 September 1977 RO NP-33-77-62:on 770825,auxiliary Feed Pump 1-1 Rendered Inoperable During Permanent Pressure Relief Valve Psv 4980 Installation.Relief Valve Installation Completed,Auxiliary Feed Pump Cooling Water Restored & Pump Declared Operable ML19329B6521977-09-26026 September 1977 RO NP-09-77-02:on 770830,during Surveillance Test,Personnel Discovered That Weekly Gaseous Grab Sample from Station Vent Monitor Was Not Obtained.Caused by Component Failure. Stack Radiation Monitor Returned to Svc ML19319B8151977-09-22022 September 1977 RO NP-33-77-59:on 770826,intermediate Range Nuclear Instrument NI-3 Disconnected from Reactor Protection Sys & Connected to Reactimeter to Perform Reactivity Measurements. NI-4 Operable During Test.Power Level Maintained at 5% ML19319B8091977-09-22022 September 1977 RO NP-33-77-64:on 770827,reactor Coolant Pump Motor 1-1-2 Tripped W/Instantaneous Ground & Differential Current Relay Indicating Fault.Caused by Damaged B&C Phase Surge Capacitors.Capacitors Repaired & Setpoints Reset ML19274D9391977-09-22022 September 1977 LER NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped,Removing One of Two Reactor Coolant Pumps from Operation.Caused by Damage to Surge Capacitors Due to Insufficient Mounting Base ML19289D5171977-09-22022 September 1977 Updated RO NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped,Removing Reactor Coolant Pump from Operation.Caused by Damaged Surge Capacitors.Capacitors on All Four Reactor Coolant Pump Motors Replaced W/Units of New Design ML19319B7861977-09-19019 September 1977 RO NP-33-77-69:on 770823,hydraulic Snubber EBD-19-H 144 Discovered Upside Down.Caused by Loose Lock Nut on Snubber Extension Piece Allowing Rotation & Placing Fluid Reservoir Below Cylinder.Snubber Purged & Tested.Lock Nut Tightened 1990-03-30 Category:LER) MONTHYEARML20042D8401990-03-30030 March 1990
[Table view]Supplement to 900105 Special Rept Re Inoperability of Diesel Fire Pump Due to Failure in Right Angle Gear Drive. Broken Studs Replaced W/Cap Screws Per Vendor Recommendations & Preventive Maint Activity Added ML20012C6861990-03-15015 March 1990 Ro:On 900204,daily Functional Test Not Done for Portable Fire Detection Sys.Caused by Shift Supervisor Failure to Ensure That Test Was Done.Requirements of Daily Functional Test Will Be Added to Operations Dept Monthly Activity Log ML20005F4401990-01-0505 January 1990 Special Rept:On 891129,diesel Fire Pump Failed While Providing Water to Support Cleaning Activity Unrelated to Fire Protection Sys.Caused by Broken Studs.Broken Studs Replaced W/Cap Screws Per Vendor Current Recommendation ML20050A9651982-03-22022 March 1982 RO NP-09-82-02:on 820222,free Chlorine Discharged in Excess of Ets,Section 2.3.1 Limit of 2-h Per Day.Caused by Equipment Deficiency.Feed Rate Will Be Verified During Chlorination Sys Lineup Changes ML20040G1191982-02-0303 February 1982 RO NP-09-82-01:on 820104,max Discharge Temp Above Ambient Lake Temp Limit Was Exceeded During Unusual Weather Change. Alarm T189 Setpoint Changed from 15 F to 17 F ML20010G3071981-08-31031 August 1981 Ro:Ie Bulletin 80-11 Analysis Determined That Listed Walls Would Be Overstressed During Seismic Event ML20005B3831981-06-25025 June 1981 RO NP-09-81-01:on 810526,max Discharge Temp Differential, Above Ambient Lake Temp,Was Slightly Exceeded.Caused by Difficulty in Maintaining Balance Between Operating to Prevent Exceeding Limit & to Prevent Cooling Tower Damage ML19350C2261981-03-17017 March 1981 Corrected Page 3 to Supplemental Info for LER 80-090 ML19341C2391981-02-18018 February 1981 Forwards Revised Supplemental Info Sheets for LER 79-050 Re Unplanned Reactivity Insertion.Caused by Mechanical, Personnel & Procedural Error.Valve Mu 39 Disassembled & Gaskets Installed ML19340C8281980-12-0101 December 1980 Supplemental Info Re RO NP-32-80-12:on 800724,w/unit in Mode 5,loss of Decay Heat Flow Observed.No Indication for Valve Position of Decay Heat Isolation Valve DH12.Revision Replaces Supplemental Info for RO 80-058 ML19345A8461980-11-18018 November 1980 Ro:On 801117 All Four Containment Pressure Transmitters Found to Be Inoperable Due to Surveillance Test Procedure Error.Emergency Tech Spec Relief Requested ML19337B4281980-09-0909 September 1980 RO NP-09-80-01:on 800116 & 0210,discharge Temp for Liquid Effluents Exceeded 20 F Above Lake Temp Due to Procedural Deficiencies.Cooling Tower Was Operated in Bypass Mode Causing Temp to Elevate Above Normal Temp During Startup ML19331B9031980-08-0404 August 1980 Ro:On 800803,heat Decay Flow Interrupted.Caused by Traveling Decay Heat Isolation Valve DH11 During Safety Features Actuation Sys Removal.Bistable Reinstalled & Pump Restarted within 3 Minutes ML19331B9001980-07-26026 July 1980 Ro:On 800724,decay Heat Flow Interrupted Twice.Caused by Inadvertently Shorted Decay Heat Isolation Valve DH12 Fuse Clip to Ground & by Tripped Output Bistable BA413 During Facility Change Request Work ML19320B9921980-06-27027 June 1980 Ro:On 800627,pipe Support HCB-40-41 on Component Cooling Water Supply to Control Rod Drive Mechanism Found Not Installed.Also,Lateral Restraint CCA-8-H15 on Pressurizer Relief Inlet Located 9 Inches from Analyzed Location ML19312E1641980-05-23023 May 1980 Ro:On 800430,chemistry & Health Physics Individual Received Dose of 4.7 Rems.Cause of Exposure Was Erroneously Low Reading on Meter or Misreading of Teletector.Individual Was Removed from Working in Radiation Controlled Areas ML19309G7341980-04-19019 April 1980 Ro:On 800418,discovered That Level of RCS Had Dropped Significantly.Control Room Operator Tripped Running Decay Heat Pump Because of Concern for Possible Loss of Suction. Caused by Vent Valve in Decay Heat Sys ML19305C9651980-04-0202 April 1980 NP-11-80-01,describing 791022 Beach Well Sample Which Indicated Tritium Concentration Three Times Beyond Normal. Procedure Changed to Require Monthly Rather than Quarterly Sampling ML19294B5191980-02-15015 February 1980 Ro:Reanalysis of RCS Pipe Restraints Revealed Less Conservative Design than Assumed on Two Reactor Coolant Hot Leg Whip Restraints Near Steam Generator Tops.Cause Unstated.Action During Refueling Outage in Eight Wks ML19296A9261980-02-12012 February 1980 RO-NP-09-80-01:on 800116,during Normal Plant Startup,Temp Differential Limit Between Station Liquid Effluent Discharge & Lake Temp Was Exceeded.Caused by Operation of Plant W/ Cooling Tower in Bypass Mode ML19276H5511979-11-13013 November 1979 Ro:On 791112,during Seismic Supports Analysis,Safety Factors on 11 Seismic Supports Found Lower than Expected.Unit Was in Cold Shutdown.Caused by Design Error in Initial Stress Calculations.Hangers Will Be Modified ML19210D7031979-11-12012 November 1979 Ro:On 791109,steam & Feedwater Rupture Control Sys Steam Generator Low Level Trip Setpoint Discovered Less Conservative than Tech Spec Requirements.Caused by Level Transmitter Setpoint Drift.Design Work Underway ML19254F9261979-11-0202 November 1979 RO-NP-09-79-06:on 791008,station Vent Recorder UJR5023 Was Inoperable.Caused by Recorder Not Advancing Paper Under Printer Due to Drive Shaft & Gear Mechanism Jam.All Ujr Recorders Will Be Replaced ML19275A5911979-09-27027 September 1979 RO NP-09-79-05:on 790831,during Review of Station Vent Data, Physicist Determined That Vent Recorder Was Inoperable. Caused by Inoperable Computer Point.Recorder Recalibr & Computer Input Card Changed ML19253A0961979-06-29029 June 1979 Notification of Violation of Tech Spec 3.4.1 on 790628. During Surveillance Testing on Reactor Protection Sys Channel 4,instrument & Control Technician Shorted Several Terminals W/Allegator Clip ML19282B7051979-02-28028 February 1979 Ro:On 790228,during Maint,Startup Transformer 01 Was de- Energized,But Addl Surveillance Required by Action Statement of Tech Spec 3.8.1.1 Was Not Performed.Caused by Personnel Oversight.Surveillance Testing Begun Approx 2-h Later ML19282A8681979-02-21021 February 1979 RO NP-09-79-04:on 790126,station Vent Monitor Re 2024 Generated Excessive Noise;Later Pump for Station Vent Monitor Re 2025 Seized.Caused by Normal Vane Wear & Low Flow During Testing.Pumps for Both Monitors Replaced ML19269C5951979-02-0101 February 1979 RO NP-09-79-02:on 790104,svc Water Sys Header Outflow Radiation Monitor Re 8432 Found Inoperable.Caused by Design Error Resulting in Component Deficiency.Flow Switch on Re 8432 Replaced & Facility Change Request Prepared ML19256A8011979-01-12012 January 1979 Reportable Occurrence NP-09-78-01:on 781215,during Routine Review of Shift Foreman'S Log,Discovered Svc Water Sys Out Header Radiation Monitor RE8432 Had Been Inoperable.Caused Apparently by Design Error.Facility Change Request Prepared ML19289C3681979-01-0505 January 1979 Reportable Occurrence NP-09-78-03 on 781209-10:discharge Temp for Station Liquid Effluents Exceeded 20 F Limit Above Lake Temp.Caused in Part by Design Deficiency in Sys Used to Determine Effluent Liquid Discharge Temp ML19256A7861979-01-0202 January 1979 to Suppl Info Sheet for LER NP-33-78-120 on 781005.Other Svc Water Valves Associated W/Component Cooling Water Heat Exchangers Were Inspected for Similar Inoperable Conditions.No Problems Noted ML19261B2121979-01-0202 January 1979 RO NP-09-79-01:on 790102,station Ventilation Radiation Monitors Re 2024 & Re 2025 Found Inoperable.Apparently Caused by Component Failure.Previous Occurrences on 770829 & 771214 Not Reported Due to Personnel Error.Units Repaired ML19263C1761978-12-15015 December 1978 RO-NP-09-78-01 on 781215:svc Water Sys Out Header Radiation Monitor Was Inoperable.Caused by Component Failure Due to Design Error.Personnel Informed of Environ Tech Specs ML20027A3751978-09-22022 September 1978 RO NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped Removing One of Two Reactor Coolant Pumps of Loop from Operation.B&C Phase Surge Capacitors Were Discovered to Be Damaged Due to Design Deficiency ML19329B0351978-07-18018 July 1978 RO 78-072-04-T-0:on 780710,station Effluent Chlorine Concentration Exceeded Tech Spec Limits.Caused by Personnel Mistakenly Returning Intake Chlorinator to Automatic Return to Svc to Be Expedited ML19317F5311978-04-17017 April 1978 Ro:On 780414,taped Electrical Terminations on Containment Air Cooler Units Found Not to Have Required LOCA Qualification.Caused by Mfg Inadequacy.Terminations to Be Reworked W/Qualified Tubing ML19317F5621978-02-24024 February 1978 Ro:On 780221,control Rod Drive Sys Trip Circuit Breaker Cabinets Found to Have Inadequate Welds.Welds to Be Lengthened to Conform W/Shaker Table Test During Apr 1978 Outage ML19317F5381977-11-16016 November 1977 Ro:On 771110,defect Discovered in Auxiliary Feed Pump Turbine Installed at Facility.Involves Potential for Governing Valve to Close While Turbine Not in Svc.Closure Caused by Excessive Vibration of Adjacent Startup Feed Pump ML19329A7821977-10-12012 October 1977 RO NP-33-77-73:on 770917,makeup Pump 1-2 Removed from Svc to Allow Repair of Oil Leak on Outboard Bearing Plate. Caused by Design Deficiency in End Plate Seal.New O-ring Installed ML19317F5351977-10-11011 October 1977 Ro:On 770930,defect Discovered in Governor on Auxiliary Feed Pumps Installed at Facility.Potential Created for Failure of Both Auxiliary Feed Pumps to Come Up to Design Speed Upon Startup.Superceded Util 771005 Ltr ML19329A8121977-10-0404 October 1977 RO NP-33-77-76:on 770901,reactor Coolant Pump 1-2-1 Tripped.Caused by Low Seal Injection & Component Cooling Water Flow,Due to Personnel Error.Instrument Air Valves Relabeled ML19329A7961977-10-0404 October 1977 RO NP-33-77-74:on 770907,decay Heat Suction Valve DH-12 Closed During Switching from Normal to Alternate Power Supply for Valve.Caused by Design Deficiency in Interlock/Control Circuit.Wiring Change in Process ML19329A8071977-09-28028 September 1977 RO NP-33-77-75:on 770829,RCS Have Less than 525 F in Mode 2,startup.Caused by Procedure Error in Shutdown Procedure & Fact That Only Three Reactor Coolant Pumps Were in Operation.Reactor Shut Down ML19319B8221977-09-27027 September 1977 RO NP-33-77-62:on 770825,auxiliary Feed Pump 1-1 Rendered Inoperable During Permanent Pressure Relief Valve Psv 4980 Installation.Relief Valve Installation Completed,Auxiliary Feed Pump Cooling Water Restored & Pump Declared Operable ML19329B6521977-09-26026 September 1977 RO NP-09-77-02:on 770830,during Surveillance Test,Personnel Discovered That Weekly Gaseous Grab Sample from Station Vent Monitor Was Not Obtained.Caused by Component Failure. Stack Radiation Monitor Returned to Svc ML19319B8151977-09-22022 September 1977 RO NP-33-77-59:on 770826,intermediate Range Nuclear Instrument NI-3 Disconnected from Reactor Protection Sys & Connected to Reactimeter to Perform Reactivity Measurements. NI-4 Operable During Test.Power Level Maintained at 5% ML19319B8091977-09-22022 September 1977 RO NP-33-77-64:on 770827,reactor Coolant Pump Motor 1-1-2 Tripped W/Instantaneous Ground & Differential Current Relay Indicating Fault.Caused by Damaged B&C Phase Surge Capacitors.Capacitors Repaired & Setpoints Reset ML19274D9391977-09-22022 September 1977 LER NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped,Removing One of Two Reactor Coolant Pumps from Operation.Caused by Damage to Surge Capacitors Due to Insufficient Mounting Base ML19289D5171977-09-22022 September 1977 Updated RO NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped,Removing Reactor Coolant Pump from Operation.Caused by Damaged Surge Capacitors.Capacitors on All Four Reactor Coolant Pump Motors Replaced W/Units of New Design ML19319B7861977-09-19019 September 1977 RO NP-33-77-69:on 770823,hydraulic Snubber EBD-19-H 144 Discovered Upside Down.Caused by Loose Lock Nut on Snubber Extension Piece Allowing Rotation & Placing Fluid Reservoir Below Cylinder.Snubber Purged & Tested.Lock Nut Tightened 1990-03-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217K1231999-10-14014 October 1999
[Table view]Revised Positions for DBNPS & PNPP QA Program ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With 05000346/LER-1998-011, :on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle1999-09-0303 September 1999
1999-09-30 |
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.. a EDISON TELECOPY October 16, 1981 TO: U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region III Attention: Mr. Leonard McGregor Davis-Besse Unit 1 Mode 1 Power (MWT) = 2772 and Load (Gross MRE) = 926 Reportabic Condition Per Technical Specification 6.9.1.8.b 1
After a request by the NRC Resident Inspector, an engineering evaluation of Sur-veillance Test ST 5030.06 revealed that the maximum string error of the pressure /
temperature bistable of the Reactor Protection System exceeded the allowable values of Technical Specification 2.2.1, Table 2.2-1. The FSAR assumed a maximum string error of 1 F and the engineering analysis revealed a maximum of 1.490F. An analy-sis by the NSSS supplic howed that the worst case DNBR was 1.416 using the maxi-mum string error oE/ 1.49 This is more conservative than the Technical Specifi-cation value of 1.3'O.
The event was determined reportable on October 16, 1981. As a precautionary measure, Facility Change Request 81-266 was implemented on October 14, 1981 resetting the pressure / temperature bistables to ensure that they were within the allowable limits.
There was no danger to the health and safety of the public or station personnel.
l l This event is being reported under Technical Specification 6.9.1.8.b.
~
Luis Reyes, NRC Resident Inspector, was contacted at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on October 16, 1981.
l
[M TELECOPY~ Sen /P.ec ved Verified R . .pt: yes no f Terry D. Murray l Station Superintendent Date /O-/0'E l Davis-Besse Nuclear Power Station 93 ,3 / g,cf> hours l
Initials 55/$b-TDM/MER/1jk j cc: Luis Reyes 820426 0 ND
! THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652 l
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