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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20148A9881997-05-0101 May 1997 Special Rept 96-04-02:on 970429,groundwater Level at Well Mk GWA-2 Was in Alarm for 7 Days.Caused by Precipitation During Previous Week.Verified That No Other Groundwater Monitoring Instruments Were in Alarm ML20137P0711997-04-0707 April 1997 Special Rept 97-01:on 970226,Peak Accelerometer,1MIMT-5030, Removed Under WO 95092624 as Part of SG Replacement Project. Accelerometer Will Return to Svc Prior to Unit 1 Startup ML20133L6051997-01-0909 January 1997 Special Rept 96-04,Rev 1,groundwater Level at Well Mk GWA-2 Monitored by 2WZLS5060 Was in Alarm for 7 Days.Verified That No Other Groundwater Monitoring Instruments in Alarm ML20134N0261996-11-14014 November 1996 Special Rept:On 961006,groundwater Alarm Was Received & Entered in TS Action Item List for Tracking.Field Survey of Surrounding Areas Was Performed to Verify That No Water Was Percolating to Surface That Would Indicate Pipe Leak ML20116K0331996-08-0909 August 1996 Special Rept 96-03:on 960611,identified Broken Secondary Contact Blocks.Caused by Mishandling of Breakers or over- Torquing of Mounting Bolts.Breaker 2BYA Repaired,Tested & re-installed in Cabinet ML20086G9601995-07-12012 July 1995 Special Rept 95-002:on 950612,turbocharger Failed,As Detected by Excessive Noise & Vibration.Engine Subsequently Secured.Damaged Components Replaced & DG 2A Returned to Operable Status ML20080G4421995-02-0303 February 1995 Special Rept 95-01:on 950104,personnel on Unit 2 Operating in Solid Condition During Fill & Vent of Nc Sys ML20078R7651994-12-15015 December 1994 Special Rept 94-06:on 941012,fatigue Usage to SI Sys Piping by Manually Initiating Flow Through B Cold Leg from Fwst During Testing for Valve 1NI-71 Intentionally Increased. Startup of Facility Discontinued to Repair Valve ML20078L6571994-11-22022 November 1994 Special Rept SR-94-05:on 941024,Channel 3 of Vibration & Loose Parts Monitoring Sys Declared Inoperable Due to Noise.Channel 3 of V&Lpm Will Be Repaired Under WR 94043758 or Replaced by Nsm MG-12096 During Outage 1EOC10 ML20073C2451994-09-14014 September 1994 Special Rept 94-004:on 940821,valid Failure of DG 1A Occurred Due to Failure of Series Boost exciter-regulator (Voltage Regulator).Isolation Transformer T54 & Current Transformers CT1,CT2 & CT3 Will Be Inspected ML20065K2501994-04-15015 April 1994 Special Rept 94-03:on 940210,during Testing PORV Observed to Hang Open in Absence of air-assisted Closure.Caused by Incomplete Testing of Porvs.Compensatory Measures Reanalyzed & Reestablished Addressing Fire & Security Issues ML20064K0311994-03-15015 March 1994 Special Rept 94-01:on 940215,DG 2A Tripped W/Low Lube Oil Pressure Indication During Routine Surveillance Test.Caused by Pressure Too Low in Bldg Up in Sensing Lines.Test Satisfactorily Repeated ML20058M4281993-09-27027 September 1993 Special Rept 93-09:on 930920,notifies of Alarm Condition Showing Alert on Ground Water Level Outside 1A DG Room.Work Order 93063348 Initiated by Wc Personnel to Have Iae Personnel Check Operation & Calibr ML20056F8561993-08-23023 August 1993 Special Rept 93-06:on 930405,discovered Debris on Unit 1 Lower Core Plate.Four Other Unidentified Objects Noted During Video Insp of Lower Core Plate ML20126B5051992-12-15015 December 1992 Inplant Review Rept 92-20,special Rept Re Postulated Scenario That Could Introduce Air Into AFW Suction Piping. Caused by Functional Design Deficiency.Setpoints of Affected Pressure Switches Increased ML20106D7401992-10-0909 October 1992 RO 92-19:on 920804,discovered That Drive Shaft on Pump 1MNVPU0046 Was Rotating in Opposite Direction than Specified on Pump Casing.Caused by Mgt Deficiency.Motor Leads of Subj Pump Reconfigured to Provide Correct Pump Shaft Rotation ML20127E0191992-09-0909 September 1992 Special Rept:On 920421,unusual Event Declared Because Unit 1 Train B of Ssps Inoperable Due to Defective Circuit Card within Ssps.Failed Train B Ssps Circuit Board Replaced & Appropriate Procedures to Be Evaluated ML20101T9441992-07-13013 July 1992 Special Rept for Inplant Review 92-10:on 920610 No Mention Made on Work List of Vent Path Through SG 1B for Incoming SG Crews.Caused by Deficient Communication.Turnover Sheet Established to Document Existing Vent Path Status ML20101P5581992-07-0303 July 1992 In-Plant Review Rept 92-09:on 920619,setpoint Problems Noted W/Ts & Selected Licensee Commitment Values for Listed Field Data.Caused by Discrepancies W/Groundwater Level Monitoring Portion of Wz Sys.Ts Monitor Logged in Unit 2 Logbook ML20086Q1101991-12-20020 December 1991 Voluntary Special Rept 91-23:on 911008,reactor Vessel Lower Internals Contacted Reactor Vessel During Removal.Caused by Inappropriate Operator Action & Mgt Deficiency.Recovery Plan Developed Re Insp of Lower Internals & Refueling Canal ML20086H9431991-12-0404 December 1991 Special Rept 91-24:on 911104-29,concerns Noted Re Possible Leakage of Containment Spray Sys Check Valves Into Annulus, Causing Offsite Radioactive Dose.Caused by Design Deficiency.Check Valve Installed Downstream of Piping ML20091C0851991-08-0101 August 1991 Special Rept PIR 1-M91-0113:on 910616,diesel Engine Cooling Water Leak Discovered on Diesel Generator 1A at Discharge Flange on Intercooler End Bell Cover.Caused by Poor Casting Quality.New Covers Will Be Installed ML20081F7371991-06-0404 June 1991 Rev 1 to Special Rept 91-11 Dtd 910411:on 910215,turbine Driven Auxiliary Feedwater Pumps Automatically Started. Caused by Deficient Communication & Lack of Attention to Detail.Pump Speed Reduced & Discharge Valves Closed ML20062E7991990-11-14014 November 1990 Special Rept:On 901011,turbine Driven Auxiliary Feedwater Pump Declared Inoperable W/O Having Made Security Notification.Caused by Inappropriate Action ML20055G2161990-07-12012 July 1990 Ro:On 900602,discovered That Channel 7 of Vibration & Loose Parts Monitor Sys Had Low Noise Level.Probably Caused by Bad or Damaged Sensor Cable.Definite Cause of Failure Undetermined.Sys Scheduled to Be Replaced ML20246F7081989-07-0303 July 1989 Special Rept:On 890601,diesel Generator 1A Shut Down Due to Lack of Oil Flow.Due to Test Being Performed,Normal Stop Would Not Shutdown Engine.New Oil Added & Pumps Primed. Turbocharger Mods Under Investigation ML20247N8841989-05-30030 May 1989 Special Rept:On 890418,vibration & Loose Parts Monitor Failed.Caused by Damaged Cables to Sensors on Each Affected Channel.Vibration & Loose Parts Monitor Will Be Repaired During Next Refueling Outage After New Replacement Received ML20244C6731989-04-0606 April 1989 Special Rept:On 890225,operations Personnel Discovered That Channel 8 of Vibration & Loose Parts Monitoring Sys Had Low Noise Level.Investigation Scheduled to Be Completed During Unit 1 Tube Leak Outage ML20196E8241988-12-0505 December 1988 Special Rept:On 881205,diesel Generator 1B Experienced Invalid Test Failure.Caused by Improper Adjustment of Voltage Regulator Due to Personnel Error.Operations Mgt Will Cover Incident W/Representative from Each Shift ML20196B5211988-11-29029 November 1988 Special Rept:On 881030,Diesel Generator 1B Experienced Invalid Test Failure During Start Attempt 602.Applicable Procedures for Diesel Generator Testing Reviewed & Revised If Necessary ML20195H4901988-11-16016 November 1988 Special Rept:On 881017,diesel Generator 1A Started for Operability Test & Subsequently Tripped.Caused by Loose Wire on Jacket Pump Discharge Pressure Switch.Wire Reterminated & Pressure Switch Calibr ML20205G3401988-10-24024 October 1988 Special Rept:On 880916,Tech Spec 3.7.14.a Violated.Caused by Standby Shutdown Facility Being Inoperable for More than 7 Days Due to Transfer Canal Isolating & Draining Utilizing Weir Gate.Special Order 88-13 Issued ML20151R0971988-07-27027 July 1988 Special Rept:On 880627,diesel Generator 1A Failed to Start within 11 S.Caused by Missing Drain Valve on Starting Air Filter Housing on Right Bank Side of Diesel Engine.Work Request Written to Replace Filter Housing ML20151F4911988-07-22022 July 1988 Special Rept:On 880519,diesel Generator 1A Started for Operability Test & After Operating for 10 Minutes, Automatically Stopped & Declared Inoperable.Caused by Failure to Maintain Lubricating Level in Valve 1LD-7 ML20195J3601988-06-22022 June 1988 Special Rept:On 880323,Train a Safety Injection & Main Steam Sys Isolation Signals Received from Unknown Fault Inside Train a Solid State Protection Sys Logic Cabinet.Cause of Fault Could Not Be Isolated.Cabinet Returned to Svc ML20195J6161988-06-20020 June 1988 Advises That Special Rept Re Diesel Generator 1A Incident on 880519 Will Be Submitted by 880708 Instead of 880620 Due to Unresolved Concerns ML20195G2171988-06-17017 June 1988 Special Rept:On 880518,diesel Generator 1B Experienced Valid Failure.Caused by Fuel & Vol of Trapped Air Shook Debris Loose from Engine Mounted Duplex Fuel Filter.Filter Cartridges Replaced.Preventative Maint Procedure Revised ML20151C7691988-04-0404 April 1988 Ro:Change of Commitment Submitted Re Diesel Generator Turbocharger Rotor Assembly Replacement.Turbocharger Inlet Casings Replaced on All Four Engines W/New Design.Dye Penetrant Testing Will Continue to Be Performed ML20147F4311988-03-0303 March 1988 Special Rept:On 880123,Channels 3,4 & 8 of Vibration & Loose Parts Monitor Had Unusual Noise Level.Cause Not Determined Due to Number of Possible Failures & Location of Components within Plants.Monitor Will Be Repaired During 1988 Outage ML20237D1341987-12-14014 December 1987 Special Rept:On 871108,safe Shutdown Facility RCS Wide Range Transmitter Out of Calibr.Instrument Could Not Be Calibrated.Requisition Initiated for Replacement Transmitter ML20236Q1621987-11-13013 November 1987 Special Rept:On 870816,malfunction of Main Turbine Generator Controls Caused Rapidly Decreasing Main Steam Line Pressure Triggering Safety Injection/Reactor Trip.Safety Injection & Unusual Event Terminated & Repairs Completed on 870821 ML20214S5421987-06-0808 June 1987 Special Rept:On 870503,pressurizer PORV 2NC-34A Automatically Opened Due to Pressure Transient in Rcs.Cause Not Determined.Charging & Letdown Flow Adjusted & Procedures Re Allowable Setpoint Range Revised ML20214G7301987-05-13013 May 1987 Special Rept:On 870407 & 08,complete 18-month Insp Required for Standby Shutdown Diesel Generator Determined Not to Have Been Performed on Time.Caused by Personnel Error.Work Request Will Be Issued Prior to 18-month Due Dates ML20213H0591987-05-0808 May 1987 Ro:On 870409,personnel Discovered Monthly Channel Checks on Reactor Vessel Level Instrumentation Sys Wide Range Instrumentation Not Performed,Per Tech Specs.Ler Will Be Submitted by 870518 ML20214J1591986-11-21021 November 1986 Ro:On 861029,valves in ECCS Declared Inoperable.Caused by Rotork Motor Switch Settings.Ler for Incident Will Be Delayed Until 861219 to Allow Testing & Evaluation of Units ML20203J6551986-07-28028 July 1986 Ro:On 860626 & 27,small Cylindrical Objects Observed on Upper Core Baffle & in Vicinity of Upender,Respectively.On 860629,objects Confirmed to Be Spent Fuel Pellets.Pellets Vacuumed from Core & Upender 1999-03-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
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DUKE POWEn GOMPANY P.O. DOX 33180 CIIAHLOTTE, N.C. 28242
, * ,f (7437 4 1 l September 3, 1987 U.S. Nuclear Regulatory Commission l
.' Document - Control" Desk" '
Washington, D.C. 20555
Subject:
McGuire Nuclear Station Decket No. 50-370 Technical Specification 4.8.1.1.3 and 6.9.2 Gentlemen:
Please find attached a special report submitted pursuant to Technical Speci-fication (T.S.) 6.9.2 as specified by T.S. 4.8.1.1.3. The report concerns Diesel Generator 2B experiencing a valid failure and two invalid failures due to slow starts.
This event is considered to be of no significance with respect to the health and safety of the public.
Very truly yours,
/
/
4 Hal B. Tucker SEL/108/jge Attachment xc: Dr. J. Nelson Grace INPO Records Center Regional Administrator, Region II 1820 Water Place U.S. Nuclear Regulatory Commission Atlanta, Ga 30339 101 Marietta St., NW, Suite 2900 Atlanta, GA 30323 Mr. Darl Hood Mr. W.T. Orders U.S. Nuclear Regulatory Commission NRC Resident Inspector Office of Nuclear Reactor Regulation McGuire Nuclear Station Washington, D.C. 20555
/ o 9709110302 870903 i I
PDR ADOCK 05000370 s PDR
Diesel Generator Special Report Diesel Generator 2B Experienced A Valid Failure .
And Two Invalid Failures Due To Slow Starts Caused By Unknown Reasons '
i INTRODUCTION:
On August 4, 1987 at 0945, Diesel Generator 2B exceeded the eleven second maximum allowable start time to achieve 4160 VAC required by Technical Specification 3/4.8.1 during a routine start for operability verification. During troubleshooting of this Valid Failure, Diesel Generator 2B also experienced two '
Invalid Test Failures due to slow start times. The cause for the. slow starts could not be determined by Instrumentation and Electrical or Mechanical Maintenance. One acceptable start time was experienced between the two Invalid Test Failures.
Three subsequent Diesel Generator 2B starts were within acceptable time limits.
Operations completed the routine operability test successfully during the third consecutive acceptable start and declared Diesel Generator 2B operable at 1910 on August 4, 1987.
1 Unit 2 was in Mode 1, Power Operations, at 100% power during the time of this incident.
This incident has been assigned a Cause Code of Other, since the root cause of the slow starts is unknown.
f EVALUATION:
Bachround Each unit at McGuire Nuclear Station has two independent diesel generators (D/Gs).
These D/Gs are used to provide standby alternating current (AC) power to the equipment required to safely shutdown the reactor in the event of a loss of normal power. The D/Gs also supply power to the safeguard equipment as required during a major accident coincident with a loss of normal power (blackout).
Technical Specification (TS) 3/4.8.1 requires both independent D/Gs to be operable in Modes 1, 2, 3, and 4. One of the routine surveillance requirements of TS 3/4.8.1 is to verify that the D/Gs start from ambient conditions and accelerate to 4160 VAC in i 11 seconds. With one D/G inoperable, the action statement requires that all required systems, subsystems, trains components, and devices that depend on the remaining operable D/G as a source of emergency power are also operable.
The action statement also requires that 2 offsite power sources are verified to be operable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter, the Steam Driven Auxiliary Feedwater Pump is demonstrated to be operable, and that the remaining D/G is demonstrated to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Table 4.8-1 of the TS specifies the '
test frequency required for D/Gs according to the number of failures in the last 20 and last 100 valid tests. If the number of failures in the last 20 valid tests is greater than or equal to 2 or the number of failures in the last 100 valid tests is greater than or equal to 5, the required test frequency increases from once each 31 days to once each 7 days.
)
Each diesel engine is controlled by a Woodward EG-B35 Governor / Actuator. There 'i are two separate sections to the Governor; the mechanical Governor section is a
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standard fly-weight type. speed sensor which modulates te hydraulic pilot valve, and the electrical Governor: ...section is an electrically operated pilot valve which responds to signals from en electronics package which measures engine speed and power. The pilot valves .in each section operate small hydraulic cylinders, which are each connected tcJ opposite ends of a lever. The middle of the lever is connected to another pilot valve, which modulates an output hydraulic cylinder.
This last hydraulic cylinder acts as a hydraulic amplifier and is connected to the fuel rack (throttle). This arrangement allows either or both of the governing sections to centrol the output to the fuel rack.
F.ach of the two sections of the Governor has its own independent speed setpoint, and the electrical section is adjusted and eet by means of a procedure. The nominal setpoint for the mechanical section is equivalent to 63 Hz, and the setpoint for the electrical section is equivalent to 59.5 Hz (60 Hz is equivalent to 514 RPM). During stea'y d state operation, the electrical section dominates and controls the engine power output with the mechanical section functioning as a backup. During an engine startup, a Servo-booster uses starting air to initially control the output to the fuel rack. At approximately 50% of rated speed, the {
l mechanical Governor assumes and essentially maintains control until approximately f 95% of rated speed. The electrical Governor may begin to assist as the diesel i approaches full speed. The fuel rack is normally maintained fully opened by the Servo-btoster and Governor during a D/G startup until full speed is attained.
s Descr y on of Incident on August 4, 1987, Operations attempted to ra "T/2/A/4350/02B, Diesel Generator "2B" Operability Test. At approximately 0940, D/G 2B was started and took 11.5 seconds to reach 4160 VAC (start No. 564, Valid Failure) . Th'e time between 95%
speed and 4160 VAC was approximately normal (1.9 seconds), but the time to reach 95% r, peed was slower than normal by approximately 1 second.
Operatious wrote a work request to have the problem investigated, and Instrwnentation and Electrical (IAE) arrived in the early afternoon to troub2eshoot for the cause of the slow start. Operations started D/G 2B at 1308 with IAE present. The D/G reached 4160 VAC in 11.3 seconds dter the start, again reaching 95% speed appro.rinately 1 second later than normal. Operations started <
D/G 2B again at 1333, and on this occasion, the D/G reached 4160 VAC within 11 j seconds. No electrical abnormalities vere observed by IAE on either of these two starts. !
I IAE.and Operations did note that the oil sight ginss level in the Governor';;uk or remained the same af ter the D/G was started, whereas Governor oil level usually decreases slightly when a D/G is started. Also, a small amount of oil was visible eround the outside of the sight glass. i
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9t 1531, Operations again started D/G 2B. This time D/G 2B reached 4160 VAC in J6,2 seconds and the diesel was audibly dragging. IAE observed the fuel rack oscillating during the time when it was supposed to remain fully open. Again the tim from 95% speed to 4160 VAC was approximately 2 seconds as expected. A " Low Crankcase Vacuum" alarm sounded and cleared a couple of seconds af ter D/G 2B was started.
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Operations then called Mechanical Maintenance (MNT) to aid in troubleshooting.
MNT observed the next three starts of D/G 2B. In all of the three starts, D/G 2B achieved 4160 VAC within 11 seconds, and MNT noted no abnormalities other than the Governor oil level increase.. MNT verified that the starting air pressure was normal and that the fuel rack was fully open during all the starts.
MNT and IAE called a Woodward Governor Company representative to discuss the possibility that ' the Governor might be' causing the slow starts. The Woodward representative did not believe the Governor was causing the problem but suggested that MNT check the vent port at the top of the Governor oil sight glass to ensure that it was not plugged. (MNT subsequently checked the port and found it open.)
On the third consecutive acceptable start, Operations completed the D/G 2B operability test successfully (start No. 570, Valid Success) and declared D/G 2B operable at 1910.
Conclusion This incident consisted of one Valid Failure and two Invalid Failures of D/G 2B.
The Valid Failure was the 6th failure in the last 100 valid attempts for D/G 2B and the 3rd failure in the last 20 valid attempts. The test frequency required by the TS for these ratios is once every 7 days , the same frequency which was required prior to this failure.
This incident has been assigned a Cause Code of Other, since the root cause of the slow starts of D/G 2B is unknown. D/G 2B has started in an acceptable amount of time in 2 starts classified as Inyslid Tests for troubleshooting and 3 starts classified as Valid Successes, since the last slow start.
-Operations is required to verify the Governor oil sight glass is full on D/G startup checklists and check that the oil level is midway on the sight glass while the D/G engine is idling. One abnormality noted during the troubleshooting of the problem with D/G 2B was that the oil level in the Governor sight glass did not decrease from full to midway when D/G 2B was started. Operations routinely see the Governor oil level decrease during starts of the other 3 D/Gs. However, the Governor on D/G 2B is a new Governor installed on May 6, 1987. The Woodward representative consulted stated that an increase in oil level in the sight glass during a start may be " normal" for this Governor. This theory is supported by the fact that the oil level has not decreased during any of the acceptable starts on August 4,1987 and af ter.
Two anomalies were noted by Operations which happened only during the 16.2 second start during troubleshooting on August 4. A " Low Crankcase Vacuum" alarm actuated a couple of seconds into this start, and the fuel rack oscillated when it should have been fully open. The reasons for these abnormalities could not be determined during troubleshooting or this investigation.
MNT conducted extensive preventive maintenance on D/G 2B from June 1, 1987 to June 16, 1987. The oil in the Governor was changed on June 13, 1987 as part of the routine maintenance. D/G 2B experienced a valid Failure due to a slow start on June 21, 1987 after the D/G post maintenance break-in runs were completed.
Although the cause of this slow start could not be determined, air in the Governor
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, ur oil lines was cited as a possible cause for this slow ~ trt. ID was, further stated that there are no provisions to bleed air from the s <.rnor oil lines after oil is added and that the DOsel would have to be operated to purge, c # any air in ,I the Govcrnor oil lines. Woodward rep 'esentatives consulted concming the June a 21, 1987 slow start said that air in the Governor oil lines r.f nt h cause slow starts, but not necessarily on the first run af ter the oil was added. Woodward representatives consulted during this investigation did not believe thab the slow starts on August 4, ,
1987 could be attributed to air in the oil lines) since 10 !
consecutive acceptable ster;ts had occurred since the oil change out. l-A review of past McGuire Reports revealed 4 other reports documenting slow starts 1 of D/Gs. A slow start of D/G 2B occurred due te a failed capacitor on the Exciter Voltage Regulator circuit card. However, the symptoms were different from the i August 4, 1987 slow starts. The time to 95% speed was normal and the time.Letween I 95% speed and 4160 VAC was longer than normal when the Fxciter Voltage Regulator malfunction occurred. /g
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- An Invalid Failure of D/G 2A ejcurred due to a slow start during a post ,
maintenance break-in run. No correctWe actions were planned since a ' slow stagt is not unexpected during a break-in run. , Another slow start of D/G 2B occurred. q for unknown reasons. No corrective Etions were planned since the . failure mpe could not be determined and subsequent'aiarts were successful. <
.Since there have been two previous slow starts of a D/G with no clear indication of a cause, this incident is considered to be recurring.
This incident is not reportable to the Nuclear Plant Reliabil ty Data System f (NPRDS).
'1 CORRECTIVE ACTIONS:
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Immediate: None
, i Subsequent: 1) The D/G 2B Operability Test was changed to require the Govarnor oil level to be verified as correct on the pre-startup checklist. '
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- 2) General Offict Nuclear maintenance observed the next routine start of D/G 2B and datermined that no further corrective t actions are needed.
Planned: None
' SAFETY ANALYSIS:
During the time that D/G 2B was inoperable, Operations performed the surveillance necessary to verify the offsite f.C power sources were ave.11able, the steam driven auxiliary feedwater pump was opierable, and that all requirtd systems, subsystems, , i trains, components, and devices that depend on f he remsging D/G as a source of emergency power were opersH4. D/G 2A was demonstrut.W operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of D/G 2B being declared di operable as required by tue TS. Therefore, there was sufficient power . available to supply the safet)-related kquipment required for:
(1) the safe shutdown of t.'y facility, and (2) , the mitigation and control of accident conditions within the, facility. f
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' There were l-- no fpersonnel . " injuries, personnel, overexposure, or releases 'of
- radioactive material as a result of this. incident.
", This. incident is considered'to#- be of' no significance with respect to ' the Walth and safety of the public, s r2 7> :2
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