ML19282A868
| ML19282A868 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/21/1979 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19282A867 | List: |
| References | |
| NUDOCS 7903070226 | |
| Download: ML19282A868 (2) | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20236U5011998-07-23023 July 1998
[Table view]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 ML20115J1121996-07-17017 July 1996 Voluntary Report:On 960430,two Unplanned Starts of Emergency Diesel Generator (EDG) 1-2 Occurred.Caused by Failure to Perform Procedural Step to Verify Power Supply to Electrical Busses D1 & D2.Personnel Counseled ML20071K6881994-07-27027 July 1994 Special Rept:On 940519,pilot Operated Relief Valve Opened for Approx 5 Seconds During Functional Testing of Replacement Reactor Trip Module in Reactor Protection Sys ML20118B9951992-10-0202 October 1992 Ro:On 920910,discovered That non-TS Hourly Fire Watch, Completed on 920908,improperly Performed,Per Suppl 1 to NRC Bulletin 92-001,resulting in Falsification of Fire Watch Log.Individual Disciplined & Addl Training Provided ML20096H0261992-05-19019 May 1992 Special Rept:On 911206,twelve Smoke Detectors in Fire Detection Zone Were Inoperable.Cause Unknown.Detectors Replaced W/Pyrotronics Model DI-6 ML20094L0651992-03-19019 March 1992 Special Rept:On 920204,local Fire Detector Alarm Panel for Fire Detection Zone Was in Trouble Indication Condition. Cause Not Determined.Hourly Fire Watch Patrol Established to Monitor Alarm ML20086K3891991-12-0606 December 1991 Supplement to 910925 Special Rept:On 910830,four Addl Alison Controls,Inc Detectors in Fire Detection Zone RCP-1,RCP-3, RZP-4 & Fdz A208 Failed.Caused by Dust Particles in Sensing Chamber.Subj Detectors Replaced W/Pyrotronics Model DI-6 ML20079F6301991-09-25025 September 1991 Special Rept:On 910818 & 0905,Fire Detection Zone A208 & Instruments Declared Inoperable When Subj Zone Panel Went Into Alarm W/No Indications of Fire.Detector Shipped to Vendor for Troubleshooting & Repair ML20073Q7671991-05-29029 May 1991 Special Rept:On 910415,ionization Type Fire Detector in Fire Detection Zone 235 (Boric Acid Evaporator Room 1-1) Inoperable.Ts 3/4.3.3.8 Entered & Hourly Fire Watch Patrol Established within 1 H ML20072U8091991-01-10010 January 1991 Special Rept:On 910304,electric Fire Pump Removed from Svc for Planned Outage for More than Seven Days.Pump Removed to Replace Existing Controller.Replacement of Controller Accomplished & Electric Fire Pump Returned to Svc ML20058M8561990-08-0606 August 1990 Ro:On 900609 & 11,station Experienced Series of Events Which Lead to Opening of Control Rod Drive Trip Breakers.Caused by Fuse Failure & Mispositioned Control Mode Selector Switch, Respectively.Test Procedure Being Modified ML20042D8401990-03-30030 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 ML20246K8931989-07-14014 July 1989 Ro:On 890314,discovered Error in Scheduling & Actual Performance of Surveillance Requirement 4.6.1.3 Re Testing for Personnel & Emergency Air Locks.Caused by Oversight. App J Exemption Request Submitted & Test Interval Changed ML20154C5271988-08-31031 August 1988 Special Rept:On 880722,Tech Spec 3.3.3.3 Violated.Caused by Accelerometers Being Inoperable for More than 30 Days.Mod 88-0060 to Replace Accelerometers Scheduled for Completion by 880915 ML20154M6751988-05-26026 May 1988 Special Rept:On 880419,diesel Fire Pump Removed from Svc for Maint & Declared Inoperable for Longer than Limit Required by Tech Spec Due to Unanticipated Temp Switch Failure.Switch Repaired & Diesel Fire Pump Declared Operable ML20236L4361987-11-0606 November 1987 Special Rept:On 870718,fire Detection Zone FDZ-A208 Declared Inoperable.Caused by Failure of Fire Detector.Hourly Fire Watch Established.Main Work Order Initiated to Repair Detector ML20236S8411987-06-12012 June 1987 Special Rept:On 870513,fire Protection Coordinator Discovered Damage to Fire Barrier Wall in Entrance to Radiation Access Control Area.Probably Caused by Personnel Negligence.Repairs to Wall Should Be Completed by 870731 ML20235B7741987-01-21021 January 1987 RO 07352:on 870121,reactor Tripped from 40% Power.Cause Not Yet Known & All Sys Functioned as Regulated for Reactor Trip ML20076J7391983-06-27027 June 1983 Ro:On 830616,hatches Associated W/Negative Pressure Boundary & Fire Barrier Removed.Notification Satisfies 30-day Requirement.Written Rept Will Be Submitted by 830713 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 ML20032C2961981-10-30030 October 1981 RO NP-09-81-02:on 811001,collection Box Discharge to Lake Exceeded Temp by Greater than Allowed 20 F.Caused by Personnel Not Taking Appropriate & Timely Action When Alarms Received.Issued Caution Memo & Alarm Change ML20054E1931981-10-16016 October 1981 Telecopy RO Re Max String Error of Pressure/Temp Bistable of Reactor Protection Sys Exceeding Allowable Values of Tech Spec 2.2.1,Table 2.2-1.Event Reported on 811016.Facility Change Request Implemented ML20010G3071981-08-31031 August 1981 Ro:Ie Bulletin 80-11 Analysis Determined That Listed Walls Would Be Overstressed During Seismic Event 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 Foremans Log,Discovered Svc Water Sys Out Header Radiation Monitor RE8432 Had Been Inoperable.Caused Apparently by Design Error.Facility Change Request Prepared 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 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 ML19261A8001978-12-19019 December 1978 RO NP-09-78-02 on 781219:RE 744 Condensate Demineralizer Backwash Receiving Tank Monitor Inoperable Since 780811. Change Request 78-431 Was Written 780818.Mods to Surveillance Tests Being Prepared ML19322D1701978-11-28028 November 1978 Ro:During 781127 Meeting W/B&W,No Requirement at Davis-Besse Found to Either Shift Back to Auto Essential Mode of Control or Manually Increase Generator Level to 120 F in Event of Small Break 1998-07-23 Category:TEXT-SAFETY REPORT MONTHYEARML20217K1231999-10-14014 October 1999
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE REPORTABLE OCCURRENCE NP-09-79-04 DATE OF EVENT: January 26, 1979 FACILITY:
Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:
Station Vent Monitors RE 2024 and RE 2025 declared inoperable.
Conditions Prior to Occurrence: The unit was in Mode 4, with Power (MWT) = 0, and Load (Gross MWE) = 0.
Description of Occurrence:
On January 22, 1979, station vent monitor RE 2024 was observed to be generating excessive noise. The monitor was secured and declared inoperable.
On January 26, 1979, during the performance of Surveillance Test ST 5032.01, "Manthly Functional Test of the Radiation Monitor System", the pump for the station vent monitor RE 2025 seized. At 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />, RE 2025 was declared inoperable.
This was not in accordance with Environmental Technical Specification 2.4.4, which requires a minimum of one monitor to continuously monitor the station vent.
Devia-tion from this requirement requires daily grab samples until the monitors are returned to service, up to seven days,at which time all releases must terminate.
Station vent monitor RE 2024 was repaired and operationally tested.
On January 26, 1979 at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />, RE 2024 was declared operational. Due to the short duration that there was no continuous sampling (less than three hours), no grab samples were taken.
Designation of Apparent Cause of Occurrence: The failure of RE 2024 was attributed to normal vane wear.
The subsequent failure of RE 2025 is believed to be a result of excessively low flow conditions during testing.
Analysis of Occurrence: There was no danger to the health and safety of the public or to unit personnel. No gaseous releases were made during the time that the sta-tion vent monitors were not available.
Corrective Action:
Under Maintenance Work Order 79-1323, the excessive noise of RE 2024 was investigated.
On January 26, 1979, the failing pump was replaced and operationally tested. The seized pump of RE 2025 was replaced under Maintenance Work Order 79-1389.
The pump was replaced and operationally tested.
On January 28, 1979, at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, RE 2025 was declared operational. Normal wear life has been established and the preventative maintenance program has been adjusted accordingly.
7008070 A2[o
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE REPORTABLE OCCURRENCE NP-09-79-04 PAGE 2 Failure Data:
Similar occurrences of radiation monitor failures were previously reported in Licensee Event Reports ':?-33-78-30, NP-33-78-143 and NP-33-78-77.
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