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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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e gggg TOLEDO EDISON A ceme or f.negy C 9www rD 50N PL A ZA
- 0) MAD! SON Avf NLL TOJDO OH!O 43GSEDOO1 NP40-92-001 AB-92-0012 Docket Number 50-346 License Number NPF-3 March 19, 1992 United States Nuclear Regulatory Commission Document Conttol Desk Vashington, D.C. 20555
Subject:
Special Report Pursuant to Technical Specification 3.3.3.8, Fire Detection Instrumentation Gentlemen:
- This letter provides the Special Report required by Davis-Besse Nuclear Power Station (DBNPS) Operating License, Appendir A, Technical Specification (TS) 3.3.3.H, Fire Detection Instrumentation, when required fire detection lustrumentation is inoperable in excess of fo ; teen days.
On February 4, 1992, "ith the reactor at 100% power (Mode 1), Toledo Edison (TE) identified that the local fire detector alarm panel (C4720A) for fire detection zone (FDZ) 317, containment batch area 585' elevation, was in a "troub]c" indication condition. This class A nmoke detection zone consists
-of twenty-six Cerberus Pyrotronics Model DI-6 ionization detectors which vere installed in the fall of 1991 during the seventh refueling outage.
Since the trouble indication condition could not be reset, FDZ 317 vas declared inoperable and the Action statement for TS 3.3.3.8 was entered.
This Action statement requires the establishment of an hourly fire watch patrol for accessible fire detection zones. Hovaver, because FDZ 317 is inside the reactor containment building and is identified on TS 3.3.3.8 Table 3.3-14 as an inac+$ ssible area, an hourly fire watch patrol was not established in FDZ 11 7 . In that the trouble indication condition for FDZ 317 on fire ~ panel C4720A prevented other trouble indication conditions (but not alatm conditions) on C4720A from being transmitted to the main control room, an hourly fire watch patrol was established to monitor C4720A for additional trouble indication cond1tions. Althougl. the trouble indication condition became intermittent after FDZ 317 vas declared inoperable TE continued to consider FDZ 317 inoperable.
This Action statement also requin , either.the restoration of the inoperable fire detection instrument to an operable status within fourteen days or-the subnission of a Special Report to the Nuclear Regulatory Commission (NRC) within the next thirty days outlining the action taken, the cause of
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~PDR ADOCK 05000346 . ,
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4 Docket Number 50-346-L(cense Number NPP-.3 7f, 'Page 2:
inoperatillity, and-the plans and~ schedule for-restoring the fire detection i
-instrument to an operable status.
During troubleshooting actions at C4720A, a monitoring system was heoked up-to the viring associated with the detectors in 12 317. The troubleshooting results indicated a reasonable-likelihood-that t a detector and/or-its
-associated base was failing. Toledo Edison evaluated the time required for troubleshooting and repair along with the expected radiation exposures and determined that the benefits of restoring FDZ 317 to an operable status were
- justified from an As Lov. As Reasonably Achievable (ALARA) program perspective. An action plan was developed to perform a containment entry in ,
Lorder to isolato and replace the failing detector / base.
On February- 21,-1992,. a containment entry was made. The time spent in FDZ 317 was kept at a minimum consistentEvith ALARA practices. One detector base was determined through testing to be inoper.able and was replaced. A new detector vas also installed in the new base. The trouble condition was
- cleared,-and, after several days of monitoring without incident, FDZ 317 was -
declared operable on February 24, 1997. .
The exact cause of detector inoperability can not be detarmined because the Ei noperable detector base can not be decontaminated sufficiently without destroying it to allov shipment to the manufacturer for a cause of failure
' evaluation. .It is being retained on site for further analysis should additional detector failures Andicate a need for root cause analysis.
If:you havelany questions, pleasa contact Mr. R. V. Schrauder, Manager -
Nuclear. Licensing, at (419) 249-2366.
, Very'truly yours, W
LL.i F. Storz .
4 ov M
~
"" Plant: Manager
~KBR/ed cei [A. B. Davis, Regional Administrator, NRC Region III i J. B. Hopkins, NRC/NRR DB-1 Senior Project Manager V. Irvis, NRC Region III, DB-1' Senior Resident Inspector Utility Radiological Safety Board
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