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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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Duxn POWER GoxnuT P.O. HOx G3180 CHARLOTTE, N.C. 28242 HALB. TUCKER TELEPHONE vion rassionwr EM) MMU ww.s. ram enonection August 8, 1986 cc cn Dr. J. Nelson Grace, Regional Administrator >
U.S. Nuclear Regulatory Commission Region II @
101 Marietta St. NW, Suite 2900 CD Atlanta, Georgia 30323 y
M
Subject:
McGuire Nuclear Station, Unit 2 --
Docket No. 50-370 cc Technical Specification 4.8.1.1.3/6.9.2 Diesel Generator Failure Special Report
Dear Dr. Grace:
Please find attached a Special Report submitted pursuant to Technical Specification 6.9.2 in fulfillment of the diesel generator failure reporting provisions of Technical Specification 4.8.1.1.3. This report concerns an invalid failure of diesel generator 2A which occurred while performing an operability test on July 9, 1986. The event was considered to be of no significance with respect to the health and safety of the public.
Very truly yours,
$8/E / W Hal B. Tucker PBN/23/jgm Attachment xc: INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 Docunent Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. W.T. Orders NRC Resident Inspector McGuire Nuclear Station 8609020007 860808 %I PDR .ADOCK 05000370 S PDR p:P
__ _ _ . _ ~ _ _ _ _ _ _ - _ . _ ._. -_ _ _ _ ,
N .
DUKE POWER COMPANY McGUIRE NUCLEAR STATION TECHkICAL SPECIFICATION 4.8.1.1.3/6.9.2 DIESEL GENERATOR FAILURE SPECIAL REPORT REPORT DATE: August 8, 1986 FACILITY: McGuire, Unit 2 IDENTIFICATION: Diesel Generator 2A Invalid Failure Due to Fire Detection Lockout -
INTRODUCTION:
On July 9, 1986, at approximately 1450, while performing an operability test on Diesel Generator (D/G) 2A, the D/G tripped (invalid failure) due to a fire detec-tion lockout actuation associated with the.D/G. Investigation determined that no fire existed, but the temperature around the fire detection heat sensors, which are located on the ceiling of the D/G room, was approximately 120 degrees F. Unit 2 was in Mode 1, Power Operation, at 100% power at the time of the incident.
The actuation of the fire detection heat sensor was a valid actuation caused by the high temperature in the D/G room. The high temperature in the D/G room was partially due to the small ventilation blower in the D/G room being inoperable since May 6, 1986. A contributing Cause was that the outside temperature was averaging near 100 degrees F during the day.
At 2115, the Emergency Stop Reset pushbutton was reset and D/G 2A restarted. The D/G was shut down at 2230 af ter successfully completing the operability test, and '
l subsequently declared operable at 2350. The small ventilation blower in the D/G
,' 2A room will be repaired.
D/G 2B was operable and available during the period in which D/G 2A'was inopera-ble. Also, after the trip on D/G 2A, the D/G would have been capable of an i
emergency start af ter the emergency stop reset pushbutton was reset. There were no personnel injuries, radiation overexposures or releases of radioactive material as a result of this incident, and the health and safety of the public were unaf-facted.
i f EVALUATION:
- i. .
! Background l Each unit at McGuire Nuclear Station has two independent diesel generators. These D/Gs are used to provide standby alternating current (AC) power to the equipment i
I i
. i 2-required to safely shut down the reactor in the event of a loss of normal power.
The D/Gs also supply power to the safeguards equipment as required during a major accident coincident with a loss of normal power (blackout).
The purpose of the Fire Detection (EFA) system is to monitor unattended areas of the station for smoke or fire and to alert plant personnel of the existence and location of a fira. The EFA system has smoke and heat sensors in the D/G room and if they detect a fire, a detection system relay is energized which energizes relays in the D/G control cabinet. These relays shut down the D/G and its oil-related auxiliaries if an emergency start relay is not energized.
- Each D/G at McGuire is housed in a separate room in the auxiliary building, and each room has its own ventilation system. During normal plant operation (the D/G not running), a small blower (3,000 cubic feet per minute) and a heating unit maintains proper room temperature. When the D/G starts, the blower is deenergized and two large fans (28,500 cubic feet per minute each) are energized.
Description of Event D/G 2A was declared inoperable at 0620 on July 9,1986 to allow installation of oil mister brackets for the starting air distributor. At 1420, after completion of the work, D/G 2A was started (start attempt 418) to perform an operability test. At approximately 1450, D/G 2A tripped due to a fire detection relay being energized (fire detection lockout actuation). This actuation not only trips the D/G (manual starts only) but also shuts down all D/G oil systems. After verifying no fire existed, start attempt 418 was declared as an invalid failure and the Emergency Stop Reset (ESR) pushbutton reset (which started the D/G oil systems and enabled the D/G to be restarted).
l Investigation of the fire detection heat sensor actuation determined the temper-
! ature near the detectors was approximately 120 degrees F (a thermocouple near the j heat sensors and a temperature gauge for the thermocouple near'the D/G local control panel were temporarily installed. The thermocouple and gauge would allow monitoring of the temperature at the heat sensors). The heat sensors are designed l to actuate at 135 degrees F and have an accuracy of approximately + 6 degrees F.
l The temperature readings were taken after the D/G room had time to cool down from I when the D/G was running. Therefore, the actuation was probably due to high temperature.
At 2115, D/G 2A was started (start attempt 419) to perform an operability test, and shut down at 2230 after successfully completing the operability test (start attempt 419 was logged as a valid success). D/G 2A was declared operable at 2350.
l A work request had previously been written on May 6,1986 to renair the small j ventilation blower in D/G 2A room (the work request was written due to the ven-l tilation blower tripping after running less than one minute). This work request
- is currently on schedule to be performed.
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i conclusion D/G 2A was inoperable from 0620 to 2350 or. July 9,1986, a total of approximately 17 1/2 hours. Investigation of the cause of the fire detection lockout determinel
.that the heat sensors were working properly. The failure during start attempt 418 was not valid; therefore, the test frequency of the Unit 2 D/Gs was not increased.
The actuation of the fire detection heat sensor was a valid actuation caused by the high temperature in the D/G room. The high temperature was partially due to the small ventilation blower in the D/G roon being inoperable. A contributing cause was the outside temperature averaging near 100 degrees F during the day.
A review of past incidents indicates there has been one incident (non reportable) involving fire detection lockouts of the D/Gs. This previous incident' occurred t
while the D/G was not running and was caused by a component failure and a personnel error. Therefore, this incident is not considered recurring. This incident is not reportable to the Nuclear Plant Reliability Data System (NPRDS).
CORRECTIVE ACTIONS:-
The small ventilation blower in D/G 2A room will be repaired. This work is currently being performed and should be completed by August 31, 1986.
l i
SAFETY ANALYSIS:
~
Technical Specification 3/4.8.1 requires that when either an offsite AC electrical power source or D/G is inoperable, the operability of the remaining power sources i be demonstrated within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter. Three j operability runs were performed on D/G 2B (while D/G 2A was inoperable) starting
- at 0615, on July 9.
i l
The operability of the AC and direct current (DC) power sources and associated
- distribution systems during plant operation ensures that there is sufficient power
- available to supply the safety-related equipment required for
- (1) the safe i shutdown of the facility, and (2) the mitigation and control of accident con-ditions within the facility. Also, the definition of operability does not make reference to emergency powar. This allows the train without emergency power (i.e.
D/G not available) to be considered operable if it has normal power and the j redundant train has emergency power and is operable.
When one D/G is inoperable, there are requirements to verity that all required i' systems, subsystems, trains, components, and devices that depend on the remaining operable D/G as a source of emergency power be operable. This provides assurance that a loss-of-offsita power event will not result in a complete loss of safety function of critical systems during the period that one of the D/Gs is inoperable.
All of these requirements were met.
f D/G 2B was operabia and available during the period in which D/G 2A was inoper-l -able. Also, after the trip on D/G 2A, the D/G would have been capable of an i
i
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, e emergency start after the Emergency Stop Reset (ESR) pushbutton, located on the D/G local control panel, was reset.
i There were no personnel injuries, radiation overexposures, or releases of radio-
- active material as a result of this incident. The health and safety of the public were not affected by this incident.
l i
l l
9 9
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