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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 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
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211A9981999-07-12012 July 1999 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
[Table view] |
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Enclosura 1 ,
h PG&E Letter DCL-96-155 l
l l-REVISION TO SPECIAL REPORT 95-03, EMERGENCY DIESEL GENERATOR 1-2 FAILURE TO SUCCESSFULLY LOAD DUE TO DEGRADED VOLTAGE REGULATOR PERFORMANCE :
In accordance with Regulatory Guide (RG) 1.108, Section C.3.b, the following l information is included:
t (1) Diesel aenerator involved: Emergency Diesel Generator (EDG) l l 1-2 l (2) As of April 1.1996. the number of valid failures in the last 100 EDG 1 1-2 valid tests: 3 i (3) Cause of failure: The root cause could not be determined based upon available evidence. The most probable cause was identified to be a loose fuse holder contact clip in the 4 kV potential transformer sensing circuit to the automatic and manual rectifier bridges and the magnetic amplifier.
(4) Corrective measures taken:
a) Immediate corrective actions: PG&E retensioned a loose fuse holder contact clip and tightened a loose wire connection at the motor operated potentiometer (MOP). At this time, PG&E successfully tested EDG 1-2 in accordance with Surveillance Test Procedure (STP) M-9A, " Diesel .
Engine Generator Routine Surveillance Test." Temporary Volts-Ampere Reactance (VAR) monitoring equipment was installed on EDG 1-2 to monitor voltage regulator input and ;
output parameters during the next monthly surveillance tests, b) To prevent recurrence: Although PG&E believes that the existing surveillance testing process, in conjunction with RG ,
1.108 requirements, provides appropriate identification of voltage regulator performance problems, the following actions will be taken to prevent recurrence:
! PG&E has revised the recurring task work orders for
- preventative maintenance (PM) on the EDG electrical
} equipment to include a step that requires maintenance
, personnel to inspect for loose fuse holder contact clips. !
9607300307 960722 -l-PDR ADOCK 05000275 S PDR -
Enclosura 1 ,
PG&E Letter DCL-96-155 I If- loose fuse holder contact clips are discovered, the fuse holder contoct clip will be retensioned and the fuse will be ,
. reinstalled.
(5) Time EDG was unavailable: EDG 1-2 was cleared to investigate i the cause of VAR fluctuations on June 22,1995, at 0140 PDT. ,
The control switch for EDG 1-2 was returned to automatic after j successful performance of STP M-9A on June 23,1995, at 0032 PDT. Thus, EDG 1-2 was unavailable for a total of 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> and 52 minutes.
(6) Current surveillance test interval: 31 days. l (7) Confirmation of proper test interval: As of April 1,1996, the total l [
number of valid failures in the last 100 valid tests for EDG 1-2 is 3, and the total number of valid failures in the last 20 valid tests for EDG 1-2 is 0; therefore, the 31 day test interval is in compliance t with the accelerated test schedule of Technical Specifications (TS)
Table 4.8-1.
- 1. Plant Conditions !
Unit 1 was in Mode 1 (Power Operation) at 100 percent power.
II. Description of Event R
A. Summary In accordance with the requirements of TS 6.9.2 and 4.8.1.1.4 and ;
Revision 1 to NRC RG 1.108, PG&E is -submitting this revision to
, Special Report 95-03 concerning failure -of EDG 1-2 to I successfully load during surveillance testing. 1 l
Using the guidance of RG 1.108, Sections B and C.2.e, this event i is considered to be a valid failure because EDG 1-2 did not successfully load due to malfunction of voltage regulation equipment that is required to be operable in the emergency operating mode. During this event, all other electrical power sources were available if called upon in the unlikely event of an actual emergency. EDG 1-2 was returned to operable status within the allowed outage time of TS 3.8.1.1 action statement b-therefore, the requirements of TS 3.8.1.1 were satisfied.
B. Background -
2- I l
i 1
Enclosuro 1 l PG&E Letter DCL-96-155 The exciter-voltage regulator provides and controls current to the y field winding of the EDG to maintain the voltage within the regulator band from no load to full load. The generator exciter-voltage regulator is designed with controls in the main control room and in the local diesel generator room. The exciter-voltage regulator is designed to operate in two modes: (1) isochronous, as l an independent source or (2) droop, in parallel with the offsite 230 kV or 500 kV systems. During performance 'of STP M-9A, the L. exciter-voltage regulator is operating in the droop mode because the EDG is paralleled through the 4160 V system to the PG&E grid.
STP M-9A implements TS 4.8.1.1.2 and is normally performed on ;
i a 31-day testing frequency. STP M-9A starts and runs each EDG for a minimum of one hour. STP M-9A is performed to demonstrate proper startup to verify that the required voltage and frequency are ,
automatically attained within acceptable limits and time. l l C. Event l- !
i l
l On June 21,1995, at 2118 PDT, testing of EDG 1-2 was initiated in ;
- accordance with STP M-9A. EDG 1-2 started, accelerated, and loaded. At 2134 PDT, VAR oscillations occurred on EDG 1-2, approximately ten minutes after paralleling to Bus G.
Subsequently, Operations reduced load and separated EDG 1-2 ;
from Bus G, shut down the EDG, and declared EDG 1-2 inoperable. Maintenance personnel began troubleshooting the l VAR fluctuations by opening the EDG voltage regulation electrical ;
panel. A loose fuse holder contact clip and a loose connection at l !
the MOP were discovered. Both connections were tightened. No l other abnormalities were identified. j 1
l On June 23,1995, at 0103 PDT, EDG 1-2 was declared operable after the successful performance of STP M-9A.
- Between June 23 and August 19,1995,17 EDG 1-2 STP M-9As
- j. were performed and no VAR swings were observed.
D. Inoperable Structures, Components, or. Systems that Contributed to the Event None.
l' i i l l
1 l
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Enclosuro 1 PG&E Letter DCL-96-155 E Dates and Approximate Times for Major Occurrences
- 1. June 21,1995, at 2134 PDT: Event / Discovery date. EDG 1-2 started per STP M-9A but did not successfully complete the surveillance test due to VAR oscillations.
- 2. June 23,1995, at 0103 PDT: EDG 1-2 was declared l operable after successful performance of STP M-9A.
F. Other Systems or Secondary Functions Affected None.
G. Method of Discovery Plant personnel identified the problem during the performance of STP M-9A.
i H. Operator Actions None.
i 1. Safety System Responses l None.
l 111. Cause of the Event l A. Immediate Cause
! PG&E has determine that the most probable immediate cause of this event was a loose fuse holder contact clip in the fuse holder in the 4 kV potential sensing circuit to the automatic and manual j rectifier bridges and the magnetic amplifier. A loose fuse holder contact clip can change the resistance of the circuit depending on the contact of the fuse to the fuse holder and affect voltage regulation.
a l
Enclosuro 1 J PG&E Letter DCL-96-155 B. Root Cause f PG&E conducted a root cause analysis including a thorough investigation into maintenance practices, a review of vendor and 1 industry operating experience, and a review of historical '
information with respect to loose MOPS and fuse holder contact !
clips on all six EDGs. However, conclusive evidence of a root ;
cause has not been found; therefore, the root cause is indeterminate.
The following categories of possible root causes for the EDG 1-2 '
valid failure were reviewed: !
- 1. Component Defects '
Both loose connections were tightened and each component .
tested satisfactorily. Thus, there is no evidence of a defect in the fuse, fuse holder contact clip, or MOP that would have' l caused or contributed to the EDG 1-2 valid failure.
- 2. Installation j Fuse holder contact clips: The original fuse holder contact :
clip tension may have been minimal. This condition may ;
have deteriorated over time during installation and removal of fuses and caused the loose fuse holder contact clip.
MOP wire: Based on interviews with Technical Maintenance- [
technicians investigating the event, the wire on the MOP ,
was verified tight during the initial troubleshooting (swing i shift) on June 21,1995. On June 22,1995, the MOP wire t was discovered loose, therefore; the loose wire connection .
was most likely caused by troubleshooting activities. ;
1 The MOP was previously inspected during the Unit 1 sixth l refueling outage (1R6), on April 10,1994. All connections were -inspected and tightened as necessary. In addition, l STP M-9A has been performed on a 31-day frequency and EDG 1-2 has never had a valid failure due to a loose electrical connection. Therefore, evidence does not exist to indicate that original installation of the wire connection caused or contributed to the EDG 1-2 valid failure.
l Enclosuro 1 PG&E Letter DCL-96-155 i4 j 3. Operating Environment i Mechanical vibration levels: The vibrational forces from an
[ operating EDG could not have caused either the fuse holder
- l' l contact clip, MOP wire connection, or components to vibrate l loose. The electrical cabinet containing both degraded j c
. omponents are mounted on the EDG room floor. Vibration
- levels at the cabinet are not large enough to loosen fuse I holder contact clip or wire terminations.
I Electrical vibratie ' levels: The vibrational forces generated j by the energizac voltage regulation circuit could not have j caused.either component to vibrate loose. The voltage and !
- power levels are not high enough to induce electrical ;
!- vibration. Therefore, evidence does not exist to indicate that i either mechanical or electrical vibrational forces caused the j- . components to loosen. ,
l 4. Routine Maintenance
+
Fuse holder contact clips: Fuses inserted and removed l l numerous time during maintenance may have changed the holder contact clip tension. Also, the fuse holder may have l
. been damaged during fuse replacement. During 1R6, on i
April 26,1994, all EDG 1-2 fuses were visually inspected .
satisfactorily. A review of historical information with respectL '
to loose fuse holder contact clips on -the EDGs has l determined that no previous events have occurred. !
Therefore, contact clips were noloosenedevidence exists during routineto support that the fusel
-maintenance.
MOP: A PM check is performed after maintenance is performed on any component in the EDG system to ensure ;
proper tightness of all wire terminations. In addition, during l every refueling outage a PM check is performed to verify i l
that all wire connections in this circuit are tight. During 1R6 on April 10,1994, all MOP -connections were inspected for tightness. Therefore, no evidence exists to indicate that the wire terminations were not tightened during the PM.
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. Enclosuro 1 PG&E Letter DCL-96-155
- 5. Vendor and Industry Operating Experience Discussions with the vendor and other industry experts indicated that the VAR oscillations could have been caused by the loose fuse holder contact clip or loose wire on the MOP.
A review of vendor and industry operating experience indicates that most EDG failures involving malfunctioning voltage regulation circuitry resulted from malfunctioning MOPS and not loose MOP connections or fuse holder . ;
contact clips. No problem with the operation of the MOP {
was found during this event.
IV. Analysis of the Event Safety-related (Class 1E) electrical loads are supplied from three 4160 V vital buses (F, G, and H) for each unit. Each vital bus can be supplied from the 500 kV switchyard, the 230 kV switchyard, the main generator, or l the EDGs. The EDGs can provide power for engineered safeguards (Class 1E) motors and loads used for emergency core cooling, reactor shutdown, and other vital safety functions when the main generator and offsite power sources are not available in the event of a loss-of-offsite power or other design-basis event.
During a design-basis event, with EDG 1-2 in a degraded condition, one bus of vital 4160 V power would not have been available for Unit 1 support. However, EDGs 1-1 and 1-3 were available to provide power to the other two Unit i vital 4160 V buses during the time that EDG 1-2 was inoperable. Subsequent to this event, EDGs 1-1 and 1-3 were successfully tested in accordance with STP M-9X, " Operability Verification."
Since only two vital buses are necessary to support Diablo Canyon Power Plant accident analysis, the health and safety of the public were not adversely affected by this event.
V. Corrective Actions i A. Immediate Corrective Actions
- 1. The voltage regulator MOP loose wire connection was tightened. The MOP was functionally tested on its full range.
4 Enclosuro 1 -
PG&E Letter DCL-96-155
- 2. The loose fuse holder contact clip holding the fuse was l retensioned to the proper tightness and the fuse was reinserted. ,
- 3. EDG 1-2 was successfully restarted and fully loaded. The VARs were verified to be fully adjustable from the control-room.
t
- 4. EDG 1-2 was successfully tested in accordance with STP M-9A.
- 5. Temporary VAR monitoring equipment was installed on EDG 1-2 to monitor voltage regulator input and output parameters during the next monthly surveillance test.
B. Corrective Actions to Prevent Recurrence The recurring task work orders for PM on the EDG electrical equipment was revised to include a step that requires maintenance ,
personnel to inspect for loose fuse holder contact clips. If a loose ,
fuse holder contact clip is discovered, the fuse holder contact clip will be retensioned and the fuse will be reinstalled t
PG&E has determined that no corrective actions are necessary to preclude a loose wire connection at the voltage regulator MOP.
The wire connection at the MOP is checked for tightness on an 18-month frequency. There is reasonable evidence to conclude the wire was loosened during troubleshooting activities and there have been no other cases of loose wire connections at the MOP.
Therefore, this event alone does not warrant an increase in the PM frequency.
VI. Additional Information A. Failed Components i
l None.
B. Previous Similar Events None. I 1
l