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| | 'XO MA[h50N AdNUL TUL E DD. D' 00 4 M2 0001 NP-40-91-03 AB-91-0034 Docket Number 50-346 License Number NPF-3 December 6, 1991 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subj ec t : Special Report Pursuant to Technical Specification 3.3.3.8, Fire Detection Instrumentation Gentlemen On September 25, 1991, Toledo Edison (TE) submitted a Special Report (NP-40-91-02) to the Nuclear Regulatory Commission (HRC) pursuant to Davis-Besse Nuclear Power Station Operating License, Appendix A, Technical Specification (TS) 3.3.3.8, Fire Dettetion Instrumentation, reporting the failure for greater than fourteen days of two smoke detectoss inanuf actured by Alison Cont rols, Inc. |
| | (ACI). These two detectors vere located in the containment annulus in Fire Detection Zone (FDZ) A208. In that Special Report, TE stated that it would provide a supplemental report to the NRC following the determination by ACI of the cause of failure of the two ACI detectors. Thit Special Report also provides a new information regarding additional inoperable ACI fire detectors. |
| | Early in Toledo Edison's seventh refueling outage, which began August 30, 1991, four additional ACI detectors in FDZ RCP-1 (Reactor Coolant Pump), FDZ RCP-3, FDZ RCP-4 and FDZ 317 (Room 317, containment hatch area) failed. Operable ACI detectors were taken from FDZ A208 and used to replace the failed detectors in order to maintain each of these other zones operable. Like the prior two failed detectors from FDZ A208, these four failed detectors were also shipped to ACI for repair. ACI determined that_four of the detectors needed a thorough cleaning to remove dust particles from the sensing chamber and two required replacement of failed transistors. |
| | Toledo Edison had pianned to replace the ACI detectors in FDZ A208 with Pyrotronics Model DI-6 detectors during the eighth refueling outen* (tentatively scheduled for Spring 1993). Ilovever, due to these ACI detector < 41ures. TE decided to replace all of the ACI detectors in FDZ A208 with the Pyrotronics Model DI-6 detectors during the seventh refueling outage. The new detectors were installed and FDZ A208 vas declared operable on November 1, 1991, prior to the end of the seventh refueling outage. |
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| | Docket Number 50-346 . |
| | License Number NPF-3 NP-40-91-03 Page 2 In addition to the ACI detector failures discussed above, on October 24, 1991, the fire detection panels for FDZ 317 (containment hatch area) and FDZ 410 (containraent building east passage) vent into spurious alatm with no other indications of fire. These two zones were declared inoperabic and hourly fire watches established in accordance with the Action Statement for TF. 3.3.3.8. At that time, the plant was in Mode 5 (Cold Shutdown), preparing for plant startup. |
| | Fire Detection Zones 317 and 410 contain twenty-six and twelve ACI detectors, ' |
| | respectively. Toledo Edison decided to replace the ACI detectors in FDZ 317 with Pyrotronics Model DI-6 detectors, and FDZ 317 was declared operable November 20, 1991. This exceeded the fourteen days allowed by TS 3.3.3.8, requiring submittal of a Special Report within thirty days (this letter satisfies that requirement). |
| | Trnubleshooting efforts vere unable to determine the cause of the alarm in FDZ 410 and the alarm could not be reset. Several of the ACI detectors removed from FDZ 317 vere used unsuccessfully in an attempt to restore FDZ 410 to an operable status. In order not to delay plant startup from the seventh refueling outage, TE decided to defer repair / replacement of the ACI detectors in FDZ 410 until the eighth refueling outage or an outage of sufficient duration. Consequently, FDZ 410 has been maintained as inoperable and the submittal of a Special Report is required (this letter satisfies that requirement). The plant entered Mode 2 (startup) on November 2, 1991 and the hourly fire watch was terminated as |
| | -allowed by-the Action Statement for TS 3.3.3.8 and TS Table 3.3-14, Fire Detection Instrumentation, due to the radiation levels in containment creating , |
| | an inaccessible condition. |
| | On November 1, 1991, a temporary modification was implemented to jumper out FDZ 410 at its fire panel to restore the capability of other fire zones to transmit an alarm to the Control Room. Due to the high radiation levels in FDZ 410 during plant operation, this zone vill remain inoperable until the eighth refueling outage or an outage of sufficient duration. After returning FDZ 410 to an operable status, a supplemental report vill be submitted describing the actions taken. |
| | If you have any questions, please contact Mr. R. V. Schrauder, Manager - Nuclear Licensing, at (419) 249-2366. |
| | Very truly yours, r-j (U Louis F. Stors Plant Manager KBR/dlm cci A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager V. Levis, NRC Region III, DB-1 Senior Resident Inspector Utility Radiological Safety Board r |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20236U5011998-07-23023 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 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
[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 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
- on 981014,manual Reactor Trip Occurred.Caused by Component Cooling Water Sys Leak.Breaker Being Installed Into D1 Bus cubicle.AACD1 Was Removed from Cubicle
ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1999-003, :on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.With1999-08-26026 August 1999
- on 990727,failure to Perform Engineering Evaluation for Pressurizer Cooldown Rate Exceeding TS Limit Was Noted.Caused by Inadequate Procedural Guidance.Provided Required Reading for Operators.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 05000346/LER-1998-013, :on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With1999-06-24024 June 1999
- on 981105,safety Valve Rupture Disks May Induce Excessive Eccentric Loading of Pressurizer Vessel Nozzles.Caused by Failure of RCS Pressure Boundary.Plant Mod Was Implemented in May of 1999.With
ML20212H9961999-06-22022 June 1999 Safety Evaluation Supporting Amend 233 to License NPF-3 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 ML20207G6661999-06-0808 June 1999 Safety Evaluation Supporting Amend 232 to License NPF-3 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 ML20206U7371999-05-19019 May 1999 Safety Evaluation Supporting Amend 231 to License NPF-3 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 05000346/LER-1999-002, :on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With1999-03-0505 March 1999
- on 990208,both Trains of Emergency Ventilation Sys Were Rendered Inoperable.Caused by Unattended Open Door. Door Was Immediately Closed Upon Discovery.With
ML20207J1461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20206U2441999-02-0909 February 1999 Safety Evaluation Supporting Amend 229 to License NPF-3 ML20199H5931999-01-20020 January 1999 Safety Evaluation Accepting Thermo-Lag Re Ampacity Derating Issues for Plant ML20199E2501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Davis-Besse Nuclear Power Station,Unit 1.With ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 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 ML20198K7671998-12-21021 December 1998 Safety Evaluation Supporting Amend 228 to License NPF-3 ML20197J3441998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-012, :on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With1998-11-17017 November 1998
- on 981018,reactor Trip Occurred from Approx 4% Power Due to ARTS Signal.Caused by Inadequate Design Drawing Resulting in Inadequate Procedure.Procedure Revised to Correct Deficiency.With
05000346/LER-1998-011, :on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With1998-11-13013 November 1998
- on 981014,manual RT Due to Ccws Leak Was Noted.Caused by Failure of One Letdown Cooler Rupture Disk. All Letdown Cooler Rupture Disks Were Replaced Prior to Plant Restart.With
05000346/LER-1998-009, :on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.With1998-11-13013 November 1998
- on 980909,RCS Pressurizer Spray Valve Was Not Functional with Two of Eight Body to Bonnet Nuts Missing. Caused by Less than Adequate Matl Separation Work Practices. Bonnet Nuts Replaced.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 05000346/LER-1998-010, :on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with1998-10-26026 October 1998
- on 980924,manual Reactor Trip Was Noted.Caused by Misdiagnosed Failure of Main FW Control Valve Solenoid Valve.Faulty Solenoid valve,SVSP6B1,was Replaced & Tested. with
05000346/LER-1998-008, :on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With1998-10-0101 October 1998
- on 981001,documented Proceduralized Guidance for Initiation of Post LOCA B Dilution Flow Path.Caused by Design Analysis Oversight.Revised Procedures to Provide Active B Dilution Flow Path Guidance.With
ML20154H5801998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Davis-Besse Nuclear Power Station,Unit 1.With 05000346/LER-1998-007, :on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With1998-09-22022 September 1998
- on 980824,CR Humidifier Ductwork Failure Caused Excessive Opening in Positive Pressure Boundary. Caused by Less than Adequate Fabrication.Evaluation of CR Humidifiers Conducted.With
ML20151W1611998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Dbnps.With 05000346/LER-1998-006, :on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources1998-08-21021 August 1998
- on 980624,loss of Offsite Power Was Noted. Caused by Tornado Damage to Switchyard.Tested & Repaired Affected Electrical & Mechanical Equipment Necessary to Restore Two Offsite Power Sources
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 05000346/LER-1998-004, :on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired1998-07-13013 July 1998
- on 980601,ductwork for Number 2 Control Room Humidifier Found Disconnected from Humidifier.Caused by Less than Adequate Connection at Humidifier Blower Housing. Ductwork Repaired
05000346/LER-1998-005, :on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations1998-07-11011 July 1998
- on 980601,both Low Pressure Injection/Dhr Pumps Were Rendered Inoperable During Testing.Caused by Inadequate Self Checking,Communication & Procedure Usage Work Practices.Operations Mgt Reviewed Expectations
ML20236M9411998-07-0707 July 1998 Safety Evaluation Supporting Amend 225 to License NPF-3 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 ML20236K4321998-06-30030 June 1998 Safety Evaluation Supporting Amend 224 to License NPF-03 ML20236N7451998-06-30030 June 1998 Monthly Operating Rept for June 1998 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 1999-09-30
[Table view] |
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'XO MA[h50N AdNUL TUL E DD. D' 00 4 M2 0001 NP-40-91-03 AB-91-0034 Docket Number 50-346 License Number NPF-3 December 6, 1991 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C. 20555 Subj ec t : Special Report Pursuant to Technical Specification 3.3.3.8, Fire Detection Instrumentation Gentlemen On September 25, 1991, Toledo Edison (TE) submitted a Special Report (NP-40-91-02) to the Nuclear Regulatory Commission (HRC) pursuant to Davis-Besse Nuclear Power Station Operating License, Appendix A, Technical Specification (TS) 3.3.3.8, Fire Dettetion Instrumentation, reporting the failure for greater than fourteen days of two smoke detectoss inanuf actured by Alison Cont rols, Inc.
(ACI). These two detectors vere located in the containment annulus in Fire Detection Zone (FDZ) A208. In that Special Report, TE stated that it would provide a supplemental report to the NRC following the determination by ACI of the cause of failure of the two ACI detectors. Thit Special Report also provides a new information regarding additional inoperable ACI fire detectors.
Early in Toledo Edison's seventh refueling outage, which began August 30, 1991, four additional ACI detectors in FDZ RCP-1 (Reactor Coolant Pump), FDZ RCP-3, FDZ RCP-4 and FDZ 317 (Room 317, containment hatch area) failed. Operable ACI detectors were taken from FDZ A208 and used to replace the failed detectors in order to maintain each of these other zones operable. Like the prior two failed detectors from FDZ A208, these four failed detectors were also shipped to ACI for repair. ACI determined that_four of the detectors needed a thorough cleaning to remove dust particles from the sensing chamber and two required replacement of failed transistors.
Toledo Edison had pianned to replace the ACI detectors in FDZ A208 with Pyrotronics Model DI-6 detectors during the eighth refueling outen* (tentatively scheduled for Spring 1993). Ilovever, due to these ACI detector < 41ures. TE decided to replace all of the ACI detectors in FDZ A208 with the Pyrotronics Model DI-6 detectors during the seventh refueling outage. The new detectors were installed and FDZ A208 vas declared operable on November 1, 1991, prior to the end of the seventh refueling outage.
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Docket Number 50-346 .
License Number NPF-3 NP-40-91-03 Page 2 In addition to the ACI detector failures discussed above, on October 24, 1991, the fire detection panels for FDZ 317 (containment hatch area) and FDZ 410 (containraent building east passage) vent into spurious alatm with no other indications of fire. These two zones were declared inoperabic and hourly fire watches established in accordance with the Action Statement for TF. 3.3.3.8. At that time, the plant was in Mode 5 (Cold Shutdown), preparing for plant startup.
Fire Detection Zones 317 and 410 contain twenty-six and twelve ACI detectors, '
respectively. Toledo Edison decided to replace the ACI detectors in FDZ 317 with Pyrotronics Model DI-6 detectors, and FDZ 317 was declared operable November 20, 1991. This exceeded the fourteen days allowed by TS 3.3.3.8, requiring submittal of a Special Report within thirty days (this letter satisfies that requirement).
Trnubleshooting efforts vere unable to determine the cause of the alarm in FDZ 410 and the alarm could not be reset. Several of the ACI detectors removed from FDZ 317 vere used unsuccessfully in an attempt to restore FDZ 410 to an operable status. In order not to delay plant startup from the seventh refueling outage, TE decided to defer repair / replacement of the ACI detectors in FDZ 410 until the eighth refueling outage or an outage of sufficient duration. Consequently, FDZ 410 has been maintained as inoperable and the submittal of a Special Report is required (this letter satisfies that requirement). The plant entered Mode 2 (startup) on November 2, 1991 and the hourly fire watch was terminated as
-allowed by-the Action Statement for TS 3.3.3.8 and TS Table 3.3-14, Fire Detection Instrumentation, due to the radiation levels in containment creating ,
an inaccessible condition.
On November 1, 1991, a temporary modification was implemented to jumper out FDZ 410 at its fire panel to restore the capability of other fire zones to transmit an alarm to the Control Room. Due to the high radiation levels in FDZ 410 during plant operation, this zone vill remain inoperable until the eighth refueling outage or an outage of sufficient duration. After returning FDZ 410 to an operable status, a supplemental report vill be submitted describing the actions taken.
If you have any questions, please contact Mr. R. V. Schrauder, Manager - Nuclear Licensing, at (419) 249-2366.
Very truly yours, r-j (U Louis F. Stors Plant Manager KBR/dlm cci A. B. Davis, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager V. Levis, NRC Region III, DB-1 Senior Resident Inspector Utility Radiological Safety Board r
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