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| " Docket No. 50-346 '~~ January 6, 1987 MEMORANDUM FOR: H. Denton ,. -
| | '~~ January 6, 1987 MEMORANDUM FOR: |
| E. Rossi. A. Thadani G. Edison | | H. Denton,. |
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| .H. Berkow J. Lyons.
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| ==SUBJECT:== | | ==SUBJECT:== |
| N'fDAILYfH!'GHi.IGHT-CMAIN FEED 6fATER PLMP FAILURE AT DAVIS-BESSE | | N'fDAILYfH!'GHi.IGHT-CMAIN FEED 6fATER PLMP FAILURE AT DAVIS-BESSE x. |
| : x. - .. $ 15 % , m~ + .a ..
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| gs.OnManuary:1d987 ~ Ce fng .atg40%,+ pow. erf. an . Anticipatory Reactor Trip .
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| .The turbine shaft and bear g'' damage will require abou 10-15 days to repair after: parts are feceivedi rts are anticipated about id-week. .
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| : m. ject Manager | | l ert De Agazio, |
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| | : m. ject Manager PWR Project Directorate #6 Division of PWR Licensing-B m |
| l ert De Agazio, PWR Project Directorate #6 .
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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
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
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
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
ML20206U7371999-05-19019 May 1999
Safety Evaluation Supporting Amend 231 to License NPF-3
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
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
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
ML20205K5781998-12-31031 December 1998
Waterhammer Phenomena in Containment Air Cooler Swss
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
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-1998-009, :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
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
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
ML20236N7451998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Davis-Besse Nuclear Power Station,Unit 1
ML20236K4321998-06-30030 June 1998
Safety Evaluation Supporting Amend 224 to License NPF-03
ML20236K5131998-06-29029 June 1998
Safety Evaluation Accepting Proposed Alternate Emergency Operations Facility Location for Davis-Besse Nuclear Power Station,Unit 1
05000346/LER-1998-003, :on 980519,Mode 3 Entry Without Completion of Surveillance Requirement Occurred.Caused by Failure of I&C Technicians to Perform Each Sp as Written or Adherence. Revised Procedure1998-06-18018 June 1998
- on 980519,Mode 3 Entry Without Completion of Surveillance Requirement Occurred.Caused by Failure of I&C Technicians to Perform Each Sp as Written or Adherence. Revised Procedure
1999-09-30
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