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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 POWER GOMPANY P.O. Box 33180 CHARL0rrrE, N.C. 28249 HAL B. TUCKER Tra.srssows vm. .. m (704)073 4831 mm. . o.
May.13, 1987 U.S. Nuclear Regulatory H DeiiniisiiinE0imirelW Desk e- G Commis si on Washington, D.C. 20555
Subject:
McGuire Nuclear-Station Docket Nos. 50-369, -370 Technical Specification 4.7.14 and 6.9.2 Gentlenen:-
Please find ' attached a special report submitted pursuant to Technical Specification (T.S.) 6.9.2 as specified by T.S. 4.7.14. The report concerns a failure to comply with proposed T.S. 4.7.14 af ter August 16, 1984 resulting in a missed commitment.
This event is considered to be of no significance with respect to the health and safety of the public.
Very truly yours .
/
dE6 e Hal B. Tucker SEL/52/jgm Attachment xc: Dr. J. Nelson Grace Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, GA 30323 Mr. Darl Hood U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. W.T. Orders INPO Records Center NRC Resident Inspector 1820 Water Place McGuire Nuclear Station 8705270157 870513 ~
Atlanta, GA 30339
[
PDR ADOCK 05000369 ##
S PDR'.
._ Duke Power Company McGuire Nuclear Station Special Report.
The Complete Eighteen' Month Inspection Required On The Standby Shutdown Facility Diesel Generator Was Not Performed On Time Due To Personnel Error .
Introduction:
During a review of the Preventive Maintenance / Periodic Test computer program,
.a determination was made on April 7 and 8, 1987, that the Standby Shutdown i Facility Diesel Generator preventive maintenance inspection was apparently not performed'within 18 months af ter the February 16, 1984 inspection. A station
!^
. commitment to comply with proposed Technical Specification 4.7.14 after August 16, 1984 requires that at least once each 18 months, the diesel must be inspected in accordance with procedures prepared from manufacturer's
- . recommendations.
Three preventive maintenance activities are recommended by the manufacturer, Cummins Engine Company Inc., to be performed once every 2 years. These three activities were performed only'during inspecticus begun on February 16, 1984 and February 27,'1986. All other preventive maintenance was performed on a frequency recommended by-the manufacturer and more frequently than each 18
- months. The 18 month interval and allowable grace period for the inspection was exceeded by 54 days beginning on January 4, 1986 because the three activities recommended by the manufacturer to be performed on a 2 year
-frequency were not performed at least once each 18 months.
i ,
{ Station personnel completed preparation oi a procedure for preventive maintenance on the Standby Shutdown Facility Diesel Generator during the
. February 27,.1986 inspection, incorporating the three items previously performed only in the 2 ' year inspection into an 18 month inspection. On April 7,;1987, station personnel changed the Preventive' Maintenance / Periodic Test schedule to delete the 1 year inspection work request and incorporate 'an
[
s 18 month inspection work request.
Units 1 and 2 were in Mode 1 Power Operations, at 100% power at the time of the discovery.
' This incident has been attributed to personnel arror because station personuel did not write the procedure and change the Preventive Maintenance Program Work i
Request schedule to perform all preventive maintenance inspection activities on the Standby Shutdown Jacility Diesel Generator at least once every 18
+
months until after the grace period expired. ,
EVALUATION:
Background
, The Standby Shutdown . Facility (SSF) Diesel Generator (D/G) provides an 4-auxiliary electrical power supply in emergency conditions. This is necessary to ensure that either unit may be brought to and maintained in the Hot Standby
} mode in the unlikely event of a_ fire or sabotage which renders the Control Roo3 and automatic safety systems inoperable.
1 1
- e v ~c.w-,.-w.,~,ce,-w-.,w-,,.w+--me.,-2-e,.en gr<-,- - . . ,,-.-vt --,<,=.we-,re -
,- :One of the requirements of proposed Technical Specification (TS) 4.7.14 is that the SSF D/G be demonstrated operable by performing an inspection at least once each 18 months in accordance with procedures prepared from the recommendations of the manufacturer of the diesel. If the surveillance interval.is exceeded,-rendering the SSF D/G technically inoperable, the action statement requires repairs be effected within 60 days or a report must be submitted to the NRC within 14 days af ter the 60 day period. McGuire Nuclear Station management committed the station to comply with the proposed TS 4.7.14 on August 16, 1984 in a letter sent out to appropriate station personnel.- The letter defined how, and by which group surveillances would be met, based on information from meetings held to discuss the issue with representatives of groups who would be required to_ fully implement the' commitment. (It has been determined since 1984 that these requirements will not be included in a TS, but will be contained in s' separate document with other fire protection i items.)
Station personnel initiated Preventive Maintenance Program Work Requests (PMP WRs) close to the time of the distribution of the letter to perform monthly, semi-annual, 1 year, and 2 year preventive maintenance inspections. The specific tasks to be performed were defined on the work requests and the manual from the manufacturer of the SSF D/G was referenced. No procedure for
- any of the work was written at the time the PMP WRs were initiated. The preventive maintenance inspection (PMI) intervals set up under the PMP WRs differ somewhat from the frequencies stated in the Cummins Engine Company, Inc. manual. Cummins representatives agreed verbally in discussions with station personnel that daily and weekly PMIs specified in the manual were unnecessary for the D/G at McGuire because of the very limited number of hours of run time the D/G receives. The representatives also concurred with station personnel that the crankshaft end clearance would only need to be checked once every 2 years for the same reason.
The McGuire Preventive Maintenance / Periodic Test (PM/PT) computer program uses
- a different calculation to determine a due date for a Periodic Test (PT) than
!~ for Preventive Maintenance (PM) work requests. The pts are usually items l required to meet a regulatory commitment. The commitment is normally
! identified in the surveillance field-on the description screen of the PM/PT
- program for that PT work request. The PMP WRs on the SSF D/Gs were not i designated as pts and no commitment reference was included in the surveillance field for these work requests.
i l
Description of Incident t
l On February 16, 1984, station personnel began work under a work request to
! perform a 2 year PMI on the SSF D/G. The work included three items
- i. recommended by the manufacturer to be performed on a 2 year frequency as well l as repeating other preventive maintenance performed more frequently. The
- three items performed only on the 2 year PMI were to check the crankshaft end clearance,-turbocharger bearing clearance, and vibration dampers.
t
! In the letter issued to station personnel on August 16, 1984 which required
( compliance with proposed TS 4.7.14, station personnel were credited with the
- February 1984 PMI (letter reads January 1984 for unknown reasons) on the SSF
[ .D/G as having initially fulfilled the requirements of step 4.7.14.1.c of the I
proposed TS. The letter also charged Maintenance personnel (MNT) with the
- - - - - ~ - - - - =. -- . - .
_ . . - - . -- - - - ~ , - ..
.. 4 I
responsibility for performing the PMI during the next outage with a procedure to be written prior to use. MNT either routed the actual proposed TS and attached letter to MNT responsible for SSF D/G maintenance (MNT. Engineer A) or by some other means informed him that he was to write the PMI procedure and ensure compliance with the commitment. . The date the assignment was made could not be determined during this investigation as no documentation was retained by MNT.
f-i MNT Engineer A recalls receiving the assignment to write the procedure, but does not recall any emphasis being placed on a deadline. He was busy with other projects at the time he was assigned the procedure and did not consider
, it to be of high enough priority to take precedence over the other work j already in progress. Shortly after the August 16, 1984 commitmentlto perform the maintenance on an 18 month frequency, the first PMP WR (semi-annual PMI) on the SSF D/G was automatically generated on August 29, 1984; the monthly and
, one year PHP WRs followed. MNT Engineer A is unsure of whether he initiated the PMP WRs before or after he received the assignment to write the procedure, but-remembered that he had planned to set up the program based on the i manufacturer's recommendations long before the implementation of the proposed
! . TS.
4 In February 1986, the first 2 yeLr PMI initiated with an automatically issued PMP WR was begun. MNT Engineer A informed the MNT crew performing the work that he was in the process of issuing a procedure for the SSF D/G PMis. The MNT crew had completed the work by referencing the manufacturer's manual as
! directed by the work request. The procedure, MP/0/B/7400/66, was approved on j March 19, 1986. MNT completed documentation of their work on the enclosure of l the new procedure and closed out the work request. The procedure addressed three PMIs to be performed on a monthly, semi-annual, and 18 month frequency.
The 18 month inspection included a requirement to perform all of the steps specified in the monthly and semi-annual sections, and all of the steps formerly performed during inspections every year and every 2 years under PMP i
WRs. No changes in frequency were made to the PMP WR after the issue of the
- new procedure changing the inspection frequencies. The MNT crew performing i
the 2 year inspection did not question the difference in the procedure and work request frequency specified.
On Mareb 24, 1987, a regularly scheduled meeting was held to discuss the PT program. At this meeting, a list of TS references was distributed which had I
been generated from a review of the PM/PT program as a corrective action from a previous incident report. Planning personnel were asked to review the list to ensure that all appropriate TS references were included in the FM/PT
, program. The SSF D/G proposed TS was included on the list.
During the course of this review on April 7th and April 8th,1987, Planning 1 personnel discovered that the SSF D/G PMP WRs were not designated as pts in i the PM/PT program and no commitment reference was listed in the surveillance i field for these work requests. Planning personnel changed the 2 year PMI to
- an 18 month PMI, deleted the PMP WR for a 1 year PMI, and added proposed TS I
4.7.14 as a reference in the surveillance field for the 18 month PMI. Upon checking the work request history, Planning personnel discovered that the
, complete PMI was not performed between February 16, 1984 and February 27, 1986, indicating that the surveillance interval of 18 months plus the grace period had been exceeded by 54 days.
Y
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Conclusion
_ The' 18 month comunitment interval was. technically exceeded because the PMP WR was not set up scheduling all SSF D/G PMI items to be performed at least once every 18 months prior to the January 4, 1986 late date; however, between February 16, 1984 and February 27, 1986, all SSF D/G PMIs were performed at least'as frequently as agreed upon with manufacturer's representatives or as specified in the Cummins Manual, MCM 1301.02-0058 002. The work is documented on completed work requests. The three inspection items which were not performed every 18 months or more frequently were the turbocharger bearing inspection, crankshaft end clearance measurement, and vibration damper inspection. The manufacturer recommends these activities be performed once every 2 years.- ' These activities were performed in February cf 1984 and February of 1986. MNT had therefore attempted to ensure adequate preventive maintenance according to manufacturer's recommendations was performed on the SSF D/G, but had not complied with the specific commitment to 18 month intervals.
MNT Engineer A is assigned a personnel error for this incident. - The' station commitment on August 16, 1984 requires that an inspection be performed at least every 18 months in accordance with procedures generated from manufacturer's recommendations.- The writing of the procedure for the PMIs was-assigned to MNT-Engineer A sometime after the August 16, 1984 letter was issued mandating compliance with the proposed TS 4.7.14. Although there is no documentation available to pinpoint the exact date of the assignment MNT Engineer A and other MNT Supervisory personnel believe that he probably received notification to write the procedure well before the expiration of the grace period on January 4,1986.
MNT Engineer A did not change the frequencies of the PMP WRs even af ter 'the procedure to perform the PMIs was completed. Until the discovery of the problem by Planning personnel on April 7, 1987, the frequencies for PMIs on the SSF D/G stood at 1 month, semi-annual,1 year, and 2 years for the automatic issue of PMP WRs. No 18 month PMP WR existed until April 7, 1987.
- It is not considered to be relevant by personnel involved in this incident-l that the PMI was not performed during the next outage after August of 1984 as l specified in the letter committing the station to the proposed TS. Although I MNT apparently did not raise the question at the time, there are no logical, i traceable reasons why it would have been necessary to schedule the 18 month l PMI only during an outage. SSF D/G PMIs are routinely performed when one or
- i. both units are in power operation, l'
This incident is not reportable to the Nuclear Plant Reliability Data System.
i A review of past McGuire reports revealed several incidents of missed periodic tests due to personnel error; therefore, this incident is considered to be recurring. The circumstances are somewhat unique in that the requirement to 1 perform the periodic test'in this case was part of a proposed commitment rather than an approved commitment.
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. Corrective Actions:
Station personnel ensured that a PMP WR to perform the inspection in its entirety be automatically issued prior to 18 month surveillance due dates.
The work request is designated as a PT and proposed TS 4.7.14 is referenced in the PM/PT computer program for that Work Request.
Safety Analysis:
The Standby Shutdown System (SSS), of which the SSF D/G is a component, exists to mitigate the effects of an accident already in progress. Inoperability of the SSF D/G would only reduce the capability to mitigate the effects of an event which disabled normal and emergency shutdown systems and rendered the Control Room uninhabitable.
Although the SSF D/G would have been considered inoperable from the January 4, 1986 late date to February 27, 1986 because an 18 month inspection was not performed in its entirety, the SSF D/G was inspected according to the manufacturer's recommendations during the time the surveillance limit was exceeded until the PMI was performed. The SSF D/G should have therefore fulfilled its design function had an accident occurred during this time period.
There were no personnel injuries, personnel overexposures, or releases of radioactive material as a result of this incident.
The health and safety of the public were not affected by this incident.
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