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Terry D. Murray Station Superintendent Davis-Besse Nuclear Power Station i Toledo. Edison Company TDM/JCS/1jk | Terry D. Murray Station Superintendent Davis-Besse Nuclear Power Station i Toledo. Edison Company TDM/JCS/1jk | ||
[0035 | [0035 | ||
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l 800 715 0 M ,3}} | l 800 715 0 M ,3}} | ||
Latest revision as of 21:00, 18 February 2020
| ML19320B992 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/27/1980 |
| From: | Murray T TOLEDO EDISON CO. |
| To: | |
| References | |
| IEB-79-14, NUDOCS 8007150609 | |
| Download: ML19320B992 (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 ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20195F4871999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20207E8011999-05-19019 May 1999 Non-proprietary Rev 2 to HI-981933, Design & Licensing Rept DBNPS Unit 1 Cask Pit Rack Installation Project ML20207F4351999-05-0404 May 1999 Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504 ML20206M6341999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Davis-Besse Nuclear Station,Unit 1.With ML20205M2931999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Davis-Besse Nuclear Power Station.With ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl ML20205K5781998-12-31031 December 1998 Waterhammer Phenomena in Containment Air Cooler Swss ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195D0001998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20155B6781998-10-28028 October 1998 Safety Evaluation Accepting Proposed Reduction in Commitment Changes in QA Program Matl Receipt Insp Process ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With ML20237E3171998-08-21021 August 1998 ISI Summary Rept of Eleventh Refueling Outage Activities for Davis-Besse Nuclear Power Station ML20237B1681998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236U5011998-07-23023 July 1998 Special Rept:On 980624,Unit 1 Site Damaged by Tornado & High Winds.Alert Declared by DBNPS Staff,Dbnps Emergency Response Facilities Activiated & Special Insp Team Deployed to Site by Nrc,As Result of Event ML20236R1441998-07-15015 July 1998 SER Related to Quality Assurance Program Description Changes for Davis-Besse Nuclear Power Station,Unit 1 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20236K3981998-06-30030 June 1998 SER Accepting in Part & Denying in Part Relief Requests from Some of ASME Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Davis-Besse Nuclear Power Station,Unit 1 ML20236K5131998-06-29029 June 1998 Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A4121998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20196B5221998-05-23023 May 1998 10CFR50.59 Summary Rept of Facility Changes,Tests & Experiments Dbnps,Unit 1 for 960602-980523 ML20236E7581998-05-19019 May 1998 Rev 0 to Davis-Besse Unit 1 Cycle 12 Colr ML20236N7501998-04-30030 April 1998 Rev 2 to Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit ML20247F6721998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Davis-Bess Nuclear Power Station,Unit 1 ML20249A4141998-04-30030 April 1998 Revised Monthly Operating Rept for Apr 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20217P8041998-04-0707 April 1998 11RFO OTSG ECT Insp Scope ML20216B4041998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20216C5131998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20202D3721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Davis-Besse Nuclear Power Station,Unit 1 ML20199G6321998-01-26026 January 1998 Rev 1 to Davis-Besse Unit 1,Cycle 11,COLR ML20198R4771998-01-13013 January 1998 SER Approving Second 10-year Interval Inservice Inspection Program Plan Requests for Relief for Davis-Besse Nuclear Power Station,Unit 1 ML20198K7931997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20217K6401997-12-31031 December 1997 1997 Annual Rept First Energy ML20203A3931997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Davis-Besse Nuclear Power Plant,Unit 1 ML20198S5371997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Davis-Besse Nuclear Power Station ML20217H7701997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Davis-Besse Nuclear Power Station,Unit 1 ML20216H3261997-08-31031 August 1997 Monthly Operating Rept for August 1997 for DBNPS ML20217K0241997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Davis Besse Nuclear Power Station,Unit 1 1999-09-30 |
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TELECOPY Ssnt/Recidvcd . - - __ _____
Verified Escoipt; (y 2 7- 9700_~,
U"" houro Jun3 27, 1980 /O /0 In tials_ M ~~
TO: U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region III Attention: Tom Tambling
SUBJECT:
Reportable Occurrence Per Technical Specification 6.9.1.8.1 Davis-Besse Unit 1 Mode 6, Power (MWT) = 0 and Load (MWE) = 0 On June 27, 1980 at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, it was determined that a found condition re-quired an immediate report.
During the detailed engineering evaluation of descrepancies found during the walkdown of inaccessible safety related piping systems required by IE Bulletin 79-14, two descrepancies were found which affect system operability. The design is less conservative than assumed in the accident analysis of the safety analysis report end is being reported under Technical Specification 6.9.1.8.1.
Pipe support HCB-40-H1 on the component cooling water (CCW) supply to the control rod drive (CRD) mechanism coolers was not installed. This would have left approximately 21 feet of 3 inch pipe between the containment penetration and the isolation valve laterally unrestrained during an earthquake. This hanger will be added under FCR 80-091, Supplement 6.
Lateral restraint CCA-8-H15 on the pressurizer relief inlet was located about 9 inches from its analyzed location. This descrepancy would have caused an over-stressed condition in a welded attachment to the line during an earthquake. This will be redesigned and relocated under FCR 80-131, Supplement 3.
Luis Reyes, Resident Inspector, was notified of this occurrence at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on June 27, 1980.
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Terry D. Murray Station Superintendent Davis-Besse Nuclear Power Station i Toledo. Edison Company TDM/JCS/1jk
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