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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000339/LER-1993-0051993-10-0404 October 1993 LER 93-005-00:on 930909,EDG Load Sequencing Timers Found Outside Setpoint Tolerence Due to Setpoint Drift.Program Established to Replace Agastat 2400/7000 Series Timer Relays w/Allen-Bradley RTC Solid State timers.W/931004 Ltr 05000339/LER-1993-0021993-08-12012 August 1993 LER 93-002-01:on 930416,automatic Trip Occurred Due to Malfunction in Main Generator Voltage Regulator Circuitry. Performed Insp of turbine/generator.W/930812 Ltr 05000338/LER-1990-0081990-06-18018 June 1990 LER 90-008-00:on 900524,discovered Design Error Where Svc Water Sys Pressures Exceeded Design Values for Anchor Piping Support on Supply Lines for Spray Hxs.Justification for Continued Operation Developed & Mods performed.W/900618 Ltr 05000338/LER-1985-026, Cancelled LER 85-026/001986-04-0909 April 1986 Cancelled LER 85-026/00 05000338/LER-1983-077, Errata to LER 83-077/03L-0,forwarding Page 2,inadvertently Omitted from Original Distribution1983-11-17017 November 1983 Errata to LER 83-077/03L-0,forwarding Page 2,inadvertently Omitted from Original Distribution 05000338/LER-1981-090, Updated LER 81-090/99X-1:on 811214,annunciators for 20.2-hertz & 25.4-hertz Vertical Axis Channels of Containment Mat Response Spectrum Recorder Illuminated & Could Not Be Reset.Cause Unknown.Unit to Be Replaced1982-06-0404 June 1982 Updated LER 81-090/99X-1:on 811214,annunciators for 20.2-hertz & 25.4-hertz Vertical Axis Channels of Containment Mat Response Spectrum Recorder Illuminated & Could Not Be Reset.Cause Unknown.Unit to Be Replaced 05000339/LER-1982-017, Updated LER 82-017/03X-1:on 820413,number of Containment Isolation Valves Had Unacceptable Leak Rate.Caused by Misaligned Limit Switches on Svc Water Valves & Seating Surface Degradation or Fouling on Other Valves1982-06-0202 June 1982 Updated LER 82-017/03X-1:on 820413,number of Containment Isolation Valves Had Unacceptable Leak Rate.Caused by Misaligned Limit Switches on Svc Water Valves & Seating Surface Degradation or Fouling on Other Valves 05000338/LER-1982-017, Updated LER 82-017/03X-1:on 820408,during Full Power, Charcoal Sample Lab Analysis from Process Vent Filter Failed to Meet Testing Criteria.Caused by Natural Depletion of Charcoal.Redundant Filter Installed & Charcoal Replaced1982-05-19019 May 1982 Updated LER 82-017/03X-1:on 820408,during Full Power, Charcoal Sample Lab Analysis from Process Vent Filter Failed to Meet Testing Criteria.Caused by Natural Depletion of Charcoal.Redundant Filter Installed & Charcoal Replaced ML20064H8611978-12-18018 December 1978 /03L-0 on 781204:during Pwr Reduction,Axial Flux Difference Deviated Greater than 5%;during Return to Full Pwr Afd Deviated Greater than -5%.Caused by Load Reduction Caused by Unit Being on Load Following ML20064H4671978-12-13013 December 1978 /01T-0 on 781130:noted That Emergency Diesel Generator Battery Racks Were Improperly Installed.Caused by Failure to Perform Requested Mods ML20064G4441978-12-0707 December 1978 /03L-0 on 781115:Detectors a & B of Incore Movable Detector Sys Stuck in Inserted Position Due to Fouled Incore Movable Detector Guide Thimbles ML20064G4541978-12-0505 December 1978 /03L-0 on 781111:during Pwr Reduction,Axial Flux Difference Deviated Greater than Tech Spec Limits.Deviation Caused by Rapid Load Reduction Caused by Failure of Turbine Governor Valve 4 to Open During Test ML20064G4341978-12-0505 December 1978 /03X-1 on 781012:during Mode 1 Opers,At 100% Pwr, Feedwater Flow Transmitter FT-1496 on Feedwater Loop C Failed Low.Caused by Blown Fuse.Fuse Subsequently Replaced ML20064G1651978-12-0101 December 1978 /03L-0 on 781110:during Critical Steady State Oper Alarms Showed High Steam Line Differential Pressure on Line B.Proper Bistables Tripped,Placing Plant in Safe Condition. Caused by Faulty Instru Loop Pwr Supply Card in Circuitry ML20064G1761978-12-0101 December 1978 /03X-1 on 780728:particulate Filter & Charcoal Filter Were Clogged.Caused by Driving Mechanism of RM-RMS-159 Filter Being Jammed ML20064F8801978-11-29029 November 1978 /01T-0 on 781116:Svc Water & Component Cooling Piping & Pipe Supports Not Analyzed for Thermal & Seismic Stresses.Design Personnel Utilized Wrong Svc Water Temps for Stress Analysis.Present Analysis Shows Adequate Support ML20064F7331978-11-27027 November 1978 /03L-0 on 781102:during Pwr Escalation,Upper Flux Deviation Alarm Was Received & Traced to a High Quadrant Pwr Tilt Ratio.Believed Cause Was Nonlinear Detector Resonse at Lower Pwr ML20064F7221978-11-27027 November 1978 /03L-0 on 781101:axial Flux Difference Deviated Greater than -5% from Target for One Minute.Caused by Pwr Reduction Necessitated by Problem with Cooling Fans on Main Station Transformer C ML20064F7261978-11-27027 November 1978 /03L-0 on 781107:during 1-pt-134 Periodic Test, MOV-QS102A Would Not Return to Normal Closed Position Because of Dirty Contacts on Valve'S Torgue Switch.Contacts Were Cleaned ML20064F7401978-11-27027 November 1978 /03L-0 on 781101:main Steam Trip Valve 1-TV-MS-111A Was Detected Leaking Due to a Deteriorated Internal Gasket.Valve Was Isolated & Gasket Replaced ML20064F2161978-11-21021 November 1978 /01T-0 on 781121:inspec of Station Battery Racks Revealed That Racks Had Been Improperly Assembled & Installed During Constr.Deficiencies Will Be Corrected ML20064F2041978-11-21021 November 1978 /01T-0 on 781113:during Steady State Oper,It Was Discovered That Only One Seal or Barrier Exists for Spare Pipe Penetrations in Conflict W/Fsar Due to Oversight of Design Personnel.Engineering Is Analyzing It for Solution ML20064F2531978-11-17017 November 1978 /03l-0 on 780927:after maint,TV-BD100A,B,D & F Were Tested But Not Timed Prior to Return to Svc,Due to Personnel Error.Personnel Have Reviewed the Requirements ML20064F2351978-11-17017 November 1978 /01X-0 on 781108:a Field Mod Was Made to Vessel Lower Head Insulation & the Mod Was Not Seismically Analyzed IAW FSAR Due to Personnel Error.Subsequently Analyzed by Stone & Webster & by Westinghouse ML20064E6781978-11-14014 November 1978 /03L-0 on 781025:During Routine Startup Oper,Axial Flux Difference Deviated Greater than 5% from target.48 Penalty Min Accumulated.Caused by Xenon Transient Occurrence.Corrective Action:Boration by Reactor Operator ML20064E4421978-11-13013 November 1978 /03X-1 on 780915:during Periodic Test,A Bistable (FC-1485 in Protec Channel Iv)Associated W/Hi Steamline Flow S.I.Actuation Failed to Trip,Due to Defective Bistable Card ML20064E4381978-11-13013 November 1978 /99X-1 on 780413:with All Rods Out at Beginning of Core Life,Hot Zero Pwr Moderator Temp Coefficient Revealed It Was More Positive than 0 Delta K/K/F in Tech Spec,Due to Positive Mtc for the all-rods-out Configuration ML20064F2411978-10-24024 October 1978 /03l-0 on 781024:following a Reactor Trip,The Containment Bulk Avg Temp Exceeded 105 Degrees F Tech Spec Limit Due to Steam Loss to Chilled Water Sys Vacuum Refrigeration Unit ML20064B9731978-10-10010 October 1978 /99X-1 on 780712:the Area Temp Monitoring Log Erroneously Recorded Excessive Temps in Battery Rooms.Cause Is Unknown ML20064B9831978-10-10010 October 1978 /03L-0 on 780905:a Bistable (FC-1485 in Protec Channel IV) Failed to Trip During a Periodic Test.Defective Bistable Card Was the Cause & Replaced ML20147B0601978-09-22022 September 1978 /03L-0 on 780830:Testing of Quench Spray Pump 1-QS-P-1B Showed Pressure Drop of Over 10psi on the Suction Line During Oper,Caused by Wooden Dam in Piping. (Encl to 7810030071) 1993-08-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210S1411999-07-31031 July 1999 Monthly Operating Repts for July 1999 for North Anna Power Station.With ML20210Q9931999-07-31031 July 1999 Rev 1 to COLR for North Anna Power Station,Unit 2 Cycle 13 Pattern Ud ML20209E5641999-06-30030 June 1999 Monthly Operating Repts for June 1999 for North Anna Power Stations,Units 1 & 2.With ML20195G1901999-05-31031 May 1999 Monthly Operating Rept for May 1999 for NAPS Units 1 & 2. with ML20206L4831999-05-10010 May 1999 SER Accepting Request to Delay Submitting Plant,Unit 1 Class 1 Piping ISI Program for Third Insp Interval Until 010430, to Permit Development of Risk Informed ISI Program for Class 1 Piping ML20206Q6671999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for North Anna Power Station,Units 1 & 2.With ML20205S0391999-04-21021 April 1999 SER Accepting Request for Relief IWE5,per 10CFR50.55a(a)(3) & Proposed Alternatives for IWE2,IWE4,IWE6 & IWL2 Authorized Per 10CFR50.55a(a)(3)(ii) ML20205K3041999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for North Anna Power Station,Units 1 & 2.With ML20207K5921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for North Anna Power Station,Units 1 & 2.With ML20207E1731999-02-18018 February 1999 Informs Commission of Status of Preparations of IAEA Osart Mission to North Anna Nuclear Power Plant Early Next Year ML20205A0241998-12-31031 December 1998 Summary of Facility Changes,Tests & Experiments,Including Summary of SEs Implemented at Plant During 1998,per 10CFR50.59(b)(2).With ML20199C8781998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for North Anna Power Station,Units 1 & 2.With ML20198H9541998-12-0303 December 1998 Safety Evaluation Authorizing Proposed Alternative for Remainder of Second 10-yr Insp Interval for Plant ML20198J5561998-12-0303 December 1998 ISI Summary Rept for North Anna Power Station,Unit 1 1998 Refueling Outage Owner Rept for Inservice Insps ML20197G8551998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for North Anna Power Station,Units 1 & 2.With ML20196G1381998-11-0303 November 1998 Safety Evaluation Authorizing Rev to Relief Request NDE-32 for Remainder of Second 10-yr Insp Interval for Each Unit ML20195D0571998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for North Anna Power Station,Units 1 & 2.With ML20154L0691998-10-14014 October 1998 COLR for North Anna Power Station Unit 1 Cycle 14 Pattern Xy ML20155J6911998-10-0909 October 1998 Staff Response to Tasking Memorandum & Stakeholder Concerns ML20154H4001998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for North Anna Power Station,Units 1 & 2.With ML20151X8011998-09-10010 September 1998 Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section ML20151W4711998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for North Anna Power Station Units 1 & 2.With ML20237A4341998-07-31031 July 1998 Monthly Operating Repts for July 1998 for North Anna Power Station,Units 1 & 2 ML20236V1251998-07-14014 July 1998 ISI Summary Rept for Naps,Unit 2,1998 Refueling Outage Owners Rept of Isis ML20236K5531998-07-0707 July 1998 SER Accepting Request for Change in ISI Commitment on Protection Against Pipe Breaks Outside Containment ML20236M3381998-06-30030 June 1998 Monthly Operating Repts for June 1998 for North Anna Power Station,Units 1 & 2 ML20248M1011998-05-31031 May 1998 Monthly Operating Repts for May 1998 for North Anna Power Station,Units 1 & 2 ML20248C8831998-05-29029 May 1998 SER Accepting Alternatives Proposed by Licensee for Use of Code Case N-535,pursuant to 10CFRa(a)(3)(i) in ASME Section XI Inservice Insp Program ML20247K9281998-05-15015 May 1998 Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary ML20216A8971998-05-0606 May 1998 Rev 0 to Cycle 13 Pattern Ud COLR for North Anna Unit 2 ML20247F4441998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for North Anna Power Station,Units 1 & 2 ML20217B5321998-04-20020 April 1998 Safety Evaluation Supporting Proposed Alternative to ASME Code for Surface Exam of Seal Welds on Threaded Caps for Plant Reactor Vessel Head Penetrations for part-length CRDMs ML20217H9611998-04-0707 April 1998 Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed ML20216B1891998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for North Anna Power Station,Units 1 & 2 ML20216E8801998-03-0606 March 1998 Safety Evaluation Authorizing Licensee Request for Relief from ASME Code Requirements,Paragraph IWA-2400(c) (Summer Edition W/Summer 1983 Addenda),For Upcoming Naps,Unit 1 Outage,Per 10CFR50.55a(a)(3)(ii) ML20216E2561998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for North Anna Power Station,Units 1 & 2 ML20199J6431998-02-0202 February 1998 Safety Evaluation Approving Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Code Class 3 SW Piping for North Anna,Unit 1,as Submitted in ISI Relief Request NDE-46 on 971218 ML20202D5811998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for North Anna Power Station,Units 1 & 2 ML20198S7571998-01-15015 January 1998 Safety Evaluation Accepting Licensee Request for Approval to Repair Flaws IAW GL-90-05 for ASME Code Class 3 Svc Water Piping ML20198P1351997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for North Anna Power Station,Units 1 & 2 1999-09-08
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8 60 61 DOCKET NUMB ER EVENT OATE EVENT DESCRIPTION AND PRO 8ABLE CONSEQUENCES h
- O l2l lFollowing a rea'ctor trip, the containment bulk average temperature exceeded the 1 0 l3 j i technical specification limit of 105 degrees F. The consequences were limited due to l lO ;4; lthe availability of Unit #1 Chilled Water System. Unit #2 Chilled Water System.had l O isi i been supplying cooling water to Unit #1 containment cooling system. I O s I -
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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h ji ioj [Following the reactor trip, Auxiliary Steam was lost which supplies steam to the 1 3 3 l vacuum refrigeration unit of the Chilled Water System. Difficulties in restartino I
- Unit #2 chiller, required that the Unit #1 chiller be put into operation. I ia l I riT41 I i
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'. Report No. LER 78-110/03L-0 Description of Event While in Mode 3 operational status on October 24, 1978, the containment bulk average temperature exceeded the plant technical specification limit of 105 F. The bulk average temperature stayed above this temperature for 72 minutes. '
This increase occurred following a reactor trip.
Consequences of Event The c.onsequences of this high Unit #1 containment bulk average temperature were limited. Each unit's Chilled Component Cooling Water Subsystem can be supplied with cooling water from either unit's Chilled Water System. When the Unit #2 Chilled Water System, which had been supplying cooling water to the Unit #1 Chilled Component Cooling Water Subsystem, failed to restart, the Unit
- 1 Chilled Water System was immediately put into operation. At no time was the public's safety or welfare endangered.
v Cause On October 24, 1978, the Unit #1 reactor tripped. This reactor trip caused the auxiliary steam supply, which provides steam to several systems, including the Chilled Water System,to be discontinued. The containment air is cooled by three. recirculation air coolers.which are supplied by Chilled Component Cooling Water Subsystem. The chilled water is cooled by the Chilled Water (CD) System, which is a steam vacuum refrigeration system.
In the event of a reactor trip, the oil fired auxiliary boilers are brought on line and used to supply auxiliary steam. Since it requires some time to get boilers up to operating temperature and pressure, auxiliary steam was not immediately available. When auxiliary steam became available, problems were encountered with restarting the Unit #2 Chiller which was supplying chilled water to the Unit #1 Chilled CC System and the Unit #1 chiller was brought on line.
( Immediate Corrective Action As soon as auxiliary steam was available, efforts were made to restart the Unit #2 chiller. When it became troublesome, the Unit #1 Chiller was put into operation. This soon brought the containment bulk average temperature under control and returned it to within the technical specification limit.
Action Taken to Prevent Recurrence To prevent recurrence of this situation, the reliability and performance of the Chilled CC and CD System must be upgraded. Currently, a redesign and improvement of these systems is underway. The main thrust of these efforts will be the addition of a mechanical chiller to the CD System.
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