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| Ycurs truly, Imb Tarry D. Murray Station' Superintendent Davis-Besse Nuclear.Powcr Station . | | Ycurs truly, Imb Tarry D. Murray Station' Superintendent Davis-Besse Nuclear.Powcr Station . |
| TDM/ljk | | TDM/ljk |
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| -Enclosure. | | -Enclosure. |
| cc: Mr. Victor Stello,-Jr.,- Director Office of Inspection and Enforcement Enc 1: 30 copies | | cc: Mr. Victor Stello,-Jr.,- Director Office of Inspection and Enforcement Enc 1: 30 copies |
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| . fill and immediately stopping the fill and investigating if any RCS boron concentra-tion problems arise. | | . fill and immediately stopping the fill and investigating if any RCS boron concentra-tion problems arise. |
| ' Additionally,^ scheduling of equipment maintenance will be more closaly coordinated between operations and maintenance persor..a1 to complete repairs in a timely basis. | | ' Additionally,^ scheduling of equipment maintenance will be more closaly coordinated between operations and maintenance persor..a1 to complete repairs in a timely basis. |
| ; Failure Data: .There has been one previously reported similar incident, refer to | | ; Failure Data: .There has been one previously reported similar incident, refer to Licensee Event Repot t NP-33-77-02. |
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| Licensee Event Repot t NP-33-77-02. | |
| 9 | | 9 |
| .LER #79-050' | | .LER #79-050' |
| -_.-v -}} | | -_.-v -}} |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20042D8401990-03-30030 March 1990 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
[Table view] Category:LER)
MONTHYEARML20042D8401990-03-30030 March 1990 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
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 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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e EDISON Fsbruny 18,!1981 L81-126 FILE: RR 2 (NP-32-79-06)
. Docket No. 50-346 i License No. NPF-3 l Mr. Ja=es G. Keppler Regional Director, Region III Office of Inspection and Enforcement U. S. Nuclear Regulatory Co=::tission
'799 Roosevelt Road Glen Ellyn, Illinois (0137
Dear Mr. Keppler:
Enclosed.are three copies of the Supplemental Information Sheets for LER 79-050, which have been revised. The revisions to'the sheets are indicated by a "1" in the left margin of each page. There has been no change to the Licensee Event Report
~ Form 366.
Please replace your previous copies of the supplemental information for LER 79-050 with the attached' revision.-
Ycurs truly, Imb Tarry D. Murray Station' Superintendent Davis-Besse Nuclear.Powcr Station .
TDM/ljk
-Enclosure.
cc: Mr. Victor Stello,-Jr.,- Director Office of Inspection and Enforcement Enc 1: 30 copies
.Mr. Norman-Haller, Director Office of Management Program Analysis Encl: 3 copies Mr. Luis Reyes
'NRC ResidentiInspector Encl: 1 copy 4
- THE TOLEDO EDISON COMPANY - EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43C52 f 01;cae20507 - , ;
1
.__.____________________________._____________'___i
d TOLEDO EDISON COMPANY ,
DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFOPJtATION FOR LER NP-32-79-06 DATE OF EVENT: April 23, 1979 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Unplanned reactivity insertion greater than 0.5%
f K/K 4
Conditions Prior to Occurrence: The unit was in Mode 5, with Power (MhT) = 0, cnd Load (Gross MWE) = 0.
Description of Occurrence: After Reactor Coolant Pump (RCP) 1-2 seal repairs were completed. Davis-Besse operations personnel commenced the Reactor Coolant System (RCS) fill at 1905 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.248525e-4 months <br /> on April 21, 1979. It was planned that 47,000 gallons of
. water from Clean Uasta Receiver Tank (CURT) 1-1 (1237 ppm boron concentration) would be pumped into the RCS (1259 ppm boron concentration) to achieve a final RCS boron concentration of 1246 ppm.
Midway through the fill, at 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br /> or. April 22, 1979, the Davis-Besse Chem Lab reported that the RCS boron concentratica was 1198 ppm. Operations personnel immed-intely verified that the decay heat flow w>s greater _than 2800 gpm, per Technical Specification 3.1.1.2,and requested another RCS ss=ple to verify the boron concen-tration reported at 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />. At 1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />, the Chem Lab reported that the bcron cencentration of the second sample was 1A94 ppm, essentially the same as the first cample.
At 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br /> on April 22, 1979, the RCS fill was stopped to find the cause of the RCS boron concentration reduction. During this. time, Boron Batch Flow Controller Velve MU 39. was leak checked and found to be closed tight. This valve was checked bicause it has been known to-Icak before. An information tag had been hung at the Btron Batch Flow Controller which read: "MU 39 leaks through; maintenance work request submitted 2-26-79". As of April 22,1979, _this work had not been completed, and this information tag was still in force. As an additional precaut.fon, Dem1nera-lized Water to Primary Makeup System Isolation Valve DW 66, which supplies deminera- i l lized water to MU 39, was also closed. Additional samples were taken from the RCS ,
cnd CWRT 1-1. The boron concentration for these samples were 1196 ppm and 1226 ppm, !
respectively. Since the RCS boron concentration had stabilized and the CWRT.1-1 l boron concentration was essentially the same as before the fill, the RCS fill was j r:sumed at 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br /> on April 22, 1979. At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, the RCS fill was complete.
On April 23, 1979, the Chem Lab verified that the RCS boron concentration was 1203 ppm. 11U 39 was leak checked again and this time'it failed. At 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> on April 23,zl979, the Davis-Besse Technical Section verified that deborating from 1259 ppm
[~ to'1198 ppm had caused an ' unplanned reactivity change of + 0.59% lin/K and estimated j L' that 3000 gallens of demineralized water had inadvertently entered the RCS. Techni-
~~~~Tcal Specification 6 .9. .1. 8 d requires that'when the reactor is subcritical, an un-planned reactivity _ insertion of more - than 0.5% 6 K/K is reportable.
l:.
LER 179-050 t
> -s _
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o TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-32-79*-06 J
Designation of Apparent Cause of Occurrence: This incident was caused by a combina-tion of mechanical, personnel and procedural error. MU 39 had experienced inter-mittent leakage problems prior to the incident. Scheduling problems prevented the repair of the valve between the initial identification of the problem with the work request and the time of the incident.
Evidence of intermittent leaking was experienced during the RCS fill. MU 39 was leaking when the fill was started on April 21, 1979, but did not leak on April 22, 1979, when it was leak checked. Again, it laaked on April 23, 1979 when the second
, leak test was performed. An operator, when lining up CWRT 1-1 to the RCS, failed to take appropriate action regarding the information on the information tag. " Filling and Venting of the RCS" SP 1103.02 did nor instruct station personnel to obtain RCS boron concentration informaticr. during the fill. This information could have indica-ted that demineralized water was inadvertently entering the RCS before any technical ,
specifications were violated.
Analysis of Occurrence: There was no danger to the health and safety of the public
-or to station personnel. Although the RCS boron concentration dropped to 1198 ppm, 3
the 0.59% A K/K reactivity insertion still resulted in a shutdown margin substantially greater than the required 1.00% d K/K shutdown nargin.
Corrective Action: When th'e RCS boron concentration was verified to be 1198 ppm, the RCS fill.was stopped, and the cause of the boron dilution was investigated. Boron Batch Flow Controller. Valve MU 39 and Demineralized Water to Primary Makeup System Isolation Valve DW 66 were closed. The RCS fill was resumed when the RCS boron con-centration stabilized.-
Und'er Maintenance Work Order 79-1586, MU39 was disassembled, the seatinE surface 1
Polished, new gaskets' installed, and the valve reassembled.- No further leakage de-tected as of May 4, 1979. Only normal seat wear observed before repair. Modifica-tion T-3751 to Filling and Venting of the RCS Operating Procedure, SP 1103.02, has been' written to close DW-66, in addition to MU 39, when lining up a CWRT to the RCS for filling.. The incident will be reviewed with all operations personnel.
" Filling and Venting of the RCS Operating Procedure", SP 1103.02 is being modified to include sampling the RCS boron concentration at four hour intervals during the
. fill and immediately stopping the fill and investigating if any RCS boron concentra-tion problems arise.
' Additionally,^ scheduling of equipment maintenance will be more closaly coordinated between operations and maintenance persor..a1 to complete repairs in a timely basis.
- Failure Data
- .There has been one previously reported similar incident, refer to Licensee Event Repot t NP-33-77-02.
9
.LER #79-050'
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