ML20202F580
From kanterella
| ML20202F580 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/01/1986 |
| From: | Shiffer J, Shiffer J PACIFIC GAS & ELECTRIC CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| DCL-86-088, DCL-86-88, SR-86-01, SR-86-1, NUDOCS 8604140179 | |
| Download: ML20202F580 (1) | |
Similar Documents at Diablo Canyon | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARDCL-96-155, Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor1996-07-22022 July 1996
[Table view]Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor ML20116B8521996-07-22022 July 1996 Revised Special Rept SR 95-04:on 950718,EDG 1-2 Load Swings Occurred.Caused by Defective Electronic Governor Stability Potentiometer.Replaced Electronic Governor ML20116B8491996-07-22022 July 1996 Revised Special Rept SR 95-03:on 950621,EDG 1-2 Failed to Load During Surveillance Testing.Caused by Loose Fuse Holder Contact Clip.Retensioned Loose Fuse Holder Contact Clip & Tightened Loose Wire Connection DCL-89-117, Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 8904181989-04-27027 April 1989 Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 890418 ML20212A0381987-02-23023 February 1987 Ro:On 870222,solid State Protection Sys Train B Removed from Svc in Excess of 2 H Tech Spec Limit.Delay Caused by Electrical Short,Resulting in Loss of Power to One of Two Redundant Trains.Power Supply Restored DCL-87-027, Special Rept 87-01:on 870126,plant Action Request Initiated After Intermittent Sys Failure Alarms Received on Train B of Reactor Vessel Level Indication Sys (Rvlis).Cause Under Investigation.Effort to Restore Train B of RVLIS Continuing1987-02-13013 February 1987 Special Rept 87-01:on 870126,plant Action Request Initiated After Intermittent Sys Failure Alarms Received on Train B of Reactor Vessel Level Indication Sys (Rvlis).Cause Under Investigation.Effort to Restore Train B of RVLIS Continuing DCL-86-355, Special Rept 86-03:on 861202,plant Vent high-range Monitor Failed in high-range.Replacement Detector Ordered & Scheduled to Arrive on 8701081986-12-15015 December 1986 Special Rept 86-03:on 861202,plant Vent high-range Monitor Failed in high-range.Replacement Detector Ordered & Scheduled to Arrive on 870108 DCL-86-312, Rev 1 to Special Rept SR 85-09:on 851223,w/unit in Mode 1, Diesel Generator Failed to Start During Performance of Surveillance Test.Caused by Dc Converter Failing to Operate Manually.Converter Replaced1986-10-24024 October 1986 Rev 1 to Special Rept SR 85-09:on 851223,w/unit in Mode 1, Diesel Generator Failed to Start During Performance of Surveillance Test.Caused by Dc Converter Failing to Operate Manually.Converter Replaced ML20210S6271986-09-26026 September 1986 Ro:On 860918,spurious Safety Injection Occurred Due to Momentary High Steam Flow Signal Concurrent W/Low RCS Average Temp.Cause Not Stated.Unit Stabilized.Corrective Action Taken to Preclude Late Reporting of Unusual Events ML20202E6691986-07-0707 July 1986 Unusual Event:On 860703,spurious Safety Injection Occurred. Caused by Momentary High Steam Flow Signal Concurrent W/Low RCS Average Temp During Preparation for Semiannual Turbine Overspeed Trip Test.Injection Terminated DCL-86-106, Special Rept SR 86-02:on 860331,main Steam Line Radiation Monitor RM-71 Inoperable for More than 7 Days.Caused by Failed Power Supply & Log Rate Circuit Boards.Alternate Radiation Monitoring Methods Established1986-04-21021 April 1986 Special Rept SR 86-02:on 860331,main Steam Line Radiation Monitor RM-71 Inoperable for More than 7 Days.Caused by Failed Power Supply & Log Rate Circuit Boards.Alternate Radiation Monitoring Methods Established DCL-86-088, Special Rept SR 86-01:on 860315,all Monitor Channels on Primary Meteorological Tower Incapacitated Due to Lightning. Temp Channels Required Replacement.On 860317,spare Processor Failed.Replacement Expected by 8604021986-04-0101 April 1986 Special Rept SR 86-01:on 860315,all Monitor Channels on Primary Meteorological Tower Incapacitated Due to Lightning. Temp Channels Required Replacement.On 860317,spare Processor Failed.Replacement Expected by 860402 ML20155A4531986-03-31031 March 1986 Ro:On 860330,manual Unit Trip Initiated Due to Occurrence of Tube Leak in Southwest Quadrant of Condenser & Safety Injection Occurred.Plant Stabilized & Unusual Event Concluded ML20140D0151986-03-17017 March 1986 Ro:On 860314,safety Injection & Subsequent Reactor Trip Occurred Due to High Steam Flow & Low Steam Line Pressure Signals.Cause Unknown.Sys Returned to Normal Status After Protection Sys Completed Safety Function DCL-86-012, Special Rept SR 85-09:on 851223,during Mode 1,diesel Generator 1-1 Failed to Start During Performance of Surveillance Test.Caused by Failure of 125-volt Dc Converter That Powers tach-pak.Converter Replaced.Procedures Revised1986-01-22022 January 1986 Special Rept SR 85-09:on 851223,during Mode 1,diesel Generator 1-1 Failed to Start During Performance of Surveillance Test.Caused by Failure of 125-volt Dc Converter That Powers tach-pak.Converter Replaced.Procedures Revised ML20138B8601985-12-0303 December 1985 Ro:On 851202,reactor Sys Experienced Unrelated Rod Position Instrumentation Indication Failure.Operators Manually Tripped Reactor.All Sys Returned to Normal Status Following Completion of Safety Functions ML20137S3121985-09-19019 September 1985 Environ Event Rept:On 850919,FEMA Notified Util of Tsunami Warning for State of CA Coast Due to Mexican Earthquake.Event Terminated.Plant Unaffected ML20099A7101985-02-13013 February 1985 Ro:On 850213,steam Line High delta-pressure Safety Injection Signal Received.Safety Injection Signal Caused ECCS to Initiate & Discharge to Rcs.Cause Under Investigation DCL-84-377, Special Rept 84-14:on 841102,Unit 1 18-month Fire Barrier Insp Identified Six Conduits & One Cable Penetration Not Sealed in Accordance W/Installation Procedure DCP 2.Fire Watch Established.Related Correspondence1984-12-0707 December 1984 Special Rept 84-14:on 841102,Unit 1 18-month Fire Barrier Insp Identified Six Conduits & One Cable Penetration Not Sealed in Accordance W/Installation Procedure DCP 2.Fire Watch Established.Related Correspondence DCL-84-306, Special Rept 84-10:on 840728,addition of Cool Feedwater to Steam Generators Resulted in Decrease in Reactor Coolant Temp to Low Setpoint.At Same Time,Hi Steam Flow Bistables Tripped for Surveillance Testing1984-09-19019 September 1984 Special Rept 84-10:on 840728,addition of Cool Feedwater to Steam Generators Resulted in Decrease in Reactor Coolant Temp to Low Setpoint.At Same Time,Hi Steam Flow Bistables Tripped for Surveillance Testing DCL-84-079, Special Rept 84-02:on 840123,fire Water Pump 1 Declared Inoperable After Pump Motor Circuit Breaker Tripped. Caused by Frequent Motor Starts in Short Time Period. Surveillance Test Conducted & Pump Returned to Svc1984-02-29029 February 1984 Special Rept 84-02:on 840123,fire Water Pump 1 Declared Inoperable After Pump Motor Circuit Breaker Tripped. Caused by Frequent Motor Starts in Short Time Period. Surveillance Test Conducted & Pump Returned to Svc DCL-84-042, Ro:On 831230,conduit Installed Through Fire Barrier Wall in Cable Spreading Room.On 840107,four Fire Doors Removed & Replaced W/Heavy Duty Fire Doors.On 840109,fire Barrier Penetrations Nonfunctional Due to Mods1984-02-0606 February 1984 Ro:On 831230,conduit Installed Through Fire Barrier Wall in Cable Spreading Room.On 840107,four Fire Doors Removed & Replaced W/Heavy Duty Fire Doors.On 840109,fire Barrier Penetrations Nonfunctional Due to Mods DCL-84-026, Ro:On 831215,fire Barrier Wall Between Containment Penetration Area & Auxiliary Bldg Removed.Wall Replaced W/Concrete Barrier for Addl Strength in Event of Steam Pipe Leak Prior to Operation1984-01-23023 January 1984 Ro:On 831215,fire Barrier Wall Between Containment Penetration Area & Auxiliary Bldg Removed.Wall Replaced W/Concrete Barrier for Addl Strength in Event of Steam Pipe Leak Prior to Operation ML20083B6751983-12-0606 December 1983 Ro:On 831205,fire Barrier Seal Discovered Nonfunctional. Patrol Established & Maint Informed of Impairment.Barrier Will Be Repaired Expeditiously.Foam Seal Not Replaced Following Support Mod Work ML20081G0931983-10-17017 October 1983 Ro:On 830916,radioactive Source Reported Missing on 830601 Found Next to Electrical Outlet Located at Floor Level in Wall Between Locker Room & Access Control ML20054L7961982-05-28028 May 1982 Ro:On 820422,fire Barrier Penetration KK871 Became Nonfunctional Due to Const Activities Required to Install New Conduit.Continuous Fire Watch Established Until Penetration Restored 1996-07-22 Category:TEXT-SAFETY REPORT MONTHYEARML20211A9981999-07-12012 July 1999
[Table view]Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure DCL-99-045, 1998 Annual Financial Rept for PG&E Corp. with1998-12-31031 December 1998 1998 Annual Financial Rept for PG&E Corp. with ML20217G5151997-12-31031 December 1997 1997 PG&E Corp Annual Rept ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18102B6911997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Diablo Canyon Power Plant,Units 1 & 2.W/970218 Ltr ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16343A4741997-01-31031 January 1997 WCAP-11595,Rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology Diablo Canyon Units 1 & 2 24 Month Fuel Cycle Evaluation. ML17083C6231997-01-31031 January 1997 Rev 4 to WCAP-13705, W Setpoint Methodology for Protection Sys Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. DCL-97-045, Pacific Gas & Electric Co 1996 Annual Rept1996-12-31031 December 1996 Pacific Gas & Electric Co 1996 Annual Rept ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary DCL-96-155, Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor1996-07-22022 July 1996 Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor ML20116B8491996-07-22022 July 1996 Revised Special Rept SR 95-03:on 950621,EDG 1-2 Failed to Load During Surveillance Testing.Caused by Loose Fuse Holder Contact Clip.Retensioned Loose Fuse Holder Contact Clip & Tightened Loose Wire Connection ML20116B8521996-07-22022 July 1996 Revised Special Rept SR 95-04:on 950718,EDG 1-2 Load Swings Occurred.Caused by Defective Electronic Governor Stability Potentiometer.Replaced Electronic Governor ML20236Q2611996-04-15015 April 1996 Rev 0 to DCP M-050284, Design Change Package for Installation of CCW Surge Tank Pressurization Sys for Unit 1 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML18064A8631995-08-14014 August 1995 LER 95-004-00:on 950714,determined That Redundant DG Circuits Not Separated Per App R Due to Insufficient App R Program Documentation.Hourly Fire Tour Established in EDG 1-1 Room & Review of LERs for App R Completed ML18100B2981994-05-24024 May 1994 LER 94-014-00:on 940426,SG 1-2 Automatically Started When Two Indicating Light Sockets Shorted Together Due to Personnel Error.Description of Event & Lessons Learned Will Be Published in Operations Incident Summary.W/940524 Ltr ML16342C3091993-12-31031 December 1993 Monthly Operating Repts for Dec 1993 for Dcnpp Units 1 & 2 ML16342A3691993-08-31031 August 1993 Revised MOR for Aug 1993 for Dcnpp Unit 1 ML16342A3681993-07-31031 July 1993 Revised MOR for July 1993 for Dcnpp Unit 1 ML20046A6611993-07-21021 July 1993 Cycle 6 Startup Rept. ML20059G6811993-06-30030 June 1993 Revised MOR for June 1993 for Dcnpp Unit 1 ML16342A3671993-05-31031 May 1993 Revised MOR for May 1993 for Dcnpp Unit 1 ML20045D1731993-05-31031 May 1993 Monthly Operating Repts for May 1993 for Diablo Canyon,Units 1 & 2 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20141M0471991-12-31031 December 1991 Pge Annual Rept - 1991 ML20086T1001991-12-31031 December 1991 Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Seismic Long-Term Program Horizontal & Vertical Ground Motions Described in Sser 34 ML16341G4871991-11-30030 November 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants. ML20085D2951991-08-21021 August 1991 Field Exercise Scenario,Aug 1991 ML20070S7311990-12-31031 December 1990 Analysis of Capsule X from Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20065R8731990-11-30030 November 1990 Monthly Operating Repts for Diablo Canyon Units 1 & 2 for Nov 1990 ML20058P5181990-05-11011 May 1990 Accident Sequence Precursor Program Event Analysis 323/87-005 R2, Loss of RHR Cooling Results in Reactor Vessel Bulk Boiling ML20058P5131990-04-0505 April 1990 Accident Sequence Precursor Program Event Analysis 424/PNO-IIT-90-02A, Loop,Diesel Generator Failure & 36 Min Interruption of SDC During Mid-Loop Operation ML20058P5221990-02-0303 February 1990 Accident Sequence Precursor Program Event Analysis Loss of Reactor Protection Sys Bus B Causes Loss of Shutdown Cooling ML20006E5441989-11-30030 November 1989 Review of Flow Peaking & Tube Fatique in Diablo Canyon Units 1 & 2 Steam Generators. ML20006C6681989-11-30030 November 1989 Nonproprietary WCAP-12416, Evaluation of Thermal Stratification for Diablo Canyon Units 1 & 2 Pressurizer Surge Line. ML20246E4891989-06-30030 June 1989 Quarterly Sys Status Rept,2nd Quarter 1989,Sys 65 120V Instrument AC Sys,Sys 66 120V Security UPS Sys & Sys 67 125/250VDC Sys ML20245G9881989-06-16016 June 1989 Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed DCL-89-117, Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 8904181989-04-27027 April 1989 Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 890418 ML20247M6281989-03-31031 March 1989 Nonproprietary Advanced Digital Feedwater Control Sys Median Signal Selector for Diablo Canyon Units 1 & 2 ML20246P4461989-03-23023 March 1989 Corrected Diablo Canyon Power Plant Unit 2 Second Refueling Outage Inservice Insp (ISI) Rept ML20236E0581988-12-31031 December 1988 Pacific Gas & Electric Co Annual Rept 1988 ML20247H0761988-11-30030 November 1988 Vol 1 to Bit Elimination Study for Diablo Canyon Units 1 & 2 ML20205S9071988-10-31031 October 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20153E5331988-08-29029 August 1988 Safety Evaluation Supporting Amends 31 & 30 to Licenses DPR-80 & DPR-82,respectively ML20206E7181988-05-30030 May 1988 Analysis of Capsule U from PG&E Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20195G3301988-04-30030 April 1988 Corrected Monthly Operating Repts for Apr 1988 for Diablo Canyon ML20153B0411988-03-31031 March 1988 Comments on ACRS Subcommittee on Diablo Canyon Meeting on 880223-24 in Burlingham,Ca Re Status of Long Term Seismic Program of Plant 1999-07-12 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML20202F580&oldid=3036631"