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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046C0821993-08-0303 August 1993 LER 93-012-00:on 930510,reported Unusual Noise Due to Small Frictional Force Release in RCS During heat-up.Developed & Implemented Enhanced Thermal Expansion Monitoring Program. W/930803 Ltr ML20045F1451993-06-30030 June 1993 LER 93-011-00:on 930518,nuclear Plant Instrumentation Sys Axial Flux Difference Limits Were Not Updated W/Ts Due to Inadequate Review of Colr.Initiated WR & Computer Software Mod request.W/930630 Ltr ML20044H0751993-06-0202 June 1993 LER 93-010-00:on 930508,Mode 3 Entered from Mode 4 W/Both MDAFWPs Rendered Inoperable by Handswitches Being Placed in pull-to-lock.Caused by Failure to Control Work Activity.Mgt Expectations clarified.W/930602 Ltr ML20045A4931993-06-0101 June 1993 LER 93-009-00:on 930504,noted That Supervising Operator Erroneously Instructed RO to Reset Steamline LP SI Signal Rather than Block SI Signal.Caused by Personnel Error. Personnel Have Been Directed to Review event.W/930601 Ltr ML20044D2821993-05-11011 May 1993 LER 93-007-00:on 930413,determined That Surveillance Test Procedure Re RHR Sys Inservice Pump B Test Not Accomplished by 930410.Caused by Lack of Oversight of Surveillance program.Past-due Notice proceduralized.W/930511 Ltr ML20045H2631992-12-31031 December 1992 LER 92-007-01:on 920326,hot Particle Discovered on Individual Left Cheek.Event Probably Occurred During Use of Plant Communications Equipment.Procedure RPP 02-510 Evaluated ML20045H2701992-04-27027 April 1992 LER 92-007-00:on 920326,hot Particle Picked Up During RCS Shim Restraint Rework Insp Results in Exposure Exceeding 10CFR20.101 Requirements.Hot Particle Control Program & Policies Being reviewed.W/920427 Ltr ML20024G9791991-05-10010 May 1991 LER 90-026-00:on 901123,tech Spec Violation Occurred Re Safety Related Class IE Battery Bank Powered from Spare Battery Charger.Caused by Error in Safety Evaluation for Procedure Mce E051Q-01.Procedure deleted.W/910510 Ltr ML20029B2361991-02-28028 February 1991 LER 91-025-01:on 901223,common Min Flow Path Return Line for SI Pumps to RWST Frozen.Caused by Faulty Ambient Temp Switch.Switches Calibr to Insure Heat Trace Circuits & Alarms activated.W/910228 Ltr ML20029A6481991-02-26026 February 1991 LER 91-002-00:on 910128,essential Svc Water Flow to Containment Cooling Units Below TS 4.6.2.3 Requirements of 4,000 Gpm.Caused by Inaccurate Flow Readings Provided by Local Annubars.Surveillance Procedure revised.W/910226 Ltr ML20028H6901991-01-22022 January 1991 LER 90-025-00:on 901223,determined That Common Min Flow Path Return Line for SI Pumps to Refueling Water Storage Tank Frozen.Cause Undetermined.Need for Effective Communications Will Be Reiterated to Plant personnel.W/910122 Ltr ML20028H4361990-12-28028 December 1990 LER 90-024-00:on 901129,portion of Contents of Waste Gas Decay Tank 6 Discharged While Maint Performed.Caused by Personnel Error.Shift Supervisor counseled.W/901228 Ltr ML20028G9191990-09-26026 September 1990 LER 90-020-00:on 900827,portable Sump Pump Installed W/Pump Discharge Directed to Storm Drains,Bypassing Turbine Bldg Drain Monitor LE-RE-59.Caused by Lack of Communication Between Involved groups.W/900926 Ltr ML20043H7201990-06-18018 June 1990 LER 90-012-00:on 900517,reactor Trip,Main Turbine Trip & Auxiliary Feedwater Actuation Signals Occurred.Caused by Steam Generator C Atmospheric Dump Valve Stuck Open. Converter Positioner Circuitry replaced.W/900618 Ltr ML20043H1531990-06-18018 June 1990 LER 90-013-00:on 900519,main Turbine Trip Occurred as Result of hi-hi Moisture Separator Reheater Level.Root Cause Investigation Not Conclusive.Cautions Added to General Operating Procedure Gen 00-004.W/900618 Ltr ML20043G2761990-06-15015 June 1990 LER 90-010-00:on 900516,discovered That Insp Access Door for Motor Driven Auxiliary Feedwater Pump B Room Cooler Had Been Removed.Caused by Personnel Error.Maint Personnel Informed of Necessity of Doors Being in place.W/900615 Ltr ML20043G0741990-06-13013 June 1990 LER 90-011-00:on 900514,feedwater Isolation Signal & Main Turbine Trip Signal Occurred When Steam Generator B Reached hi-hi Level Setpoint & Generator C Reached lo-lo Setpoint. Caused by Power Oscillations.Procedure revised.W/900613 Ltr ML20043G1991990-06-0808 June 1990 LER 90-007-00:on 900510,feedwater Isolation Signal Occurred Due to Surveillance Test Requiring High Feed Rate.Caused by Feedwater Flow Rate Higher than Steam Flow.Rev to Surveillance Test Procedures clarified.W/900608 Ltr ML20043E9551990-06-0808 June 1990 LER 90-009-00:on 900608,discovered That Circuit Breakers for Accumulator Outlet IV Closed Resulting in Two Inoperable Accumulators.Caused by Personnel Error & Lack of Specific Procedural Direction.Procedure revised.W/900608 Ltr ML20043F1581990-06-0404 June 1990 LER 90-008-00:on 900504,fuel Bldg/Control Room Ventilation Isolation Signals Received from Exhaust Radiation Monitor. Caused by Burned Out Lamp & Blown Fuse in Power Supply.Fuse & Lamp Replaced & Monitor Returned to svc.W/900604 Ltr ML20043A6731990-05-16016 May 1990 LER 90-006-00:on 900416,containment Purge Isolation Signal & Control Room Ventilation Isolation Signal Occurred.Caused by Inadequate Procedures to Govern Deenergization of 120- Volt Ac Distribution Ctrs.Procedures revised.W/900516 Ltr ML20042G9171990-05-10010 May 1990 LER 90-005-00:on 900410,control Bldg/Auxiliary Bldg Pressure Boundary Door Found Open W/O Continuous Watch Established. Caused by Inadequate Procedures.Fire Protection Impairment Control Procedure revised.W/900510 Ltr ML20042G2131990-05-0707 May 1990 LER 90-004-00:on 900405,Tech Spec Surveillance Requirement Not Satisfied Because of Personnel Error in Scheduling Surveillance Test.Procedure Adm 02-300 revised.W/900507 Ltr ML20042E1851990-04-13013 April 1990 LER 90-002-00:on 900314,determined That Halon Release in Either ESF Switchgear Room Would Trip Both Class 1E Electrical Equipment Air Conditioning Units.Caused by Lack of Design Criteria.Criteria revised.W/900413 Ltr ML20043H2871990-04-0909 April 1990 Corrected LER 85-058-01:on 850731,reactor Trip,Main Turbine Trip,Auxiliary Feedwater Actuation,Feedwater Isolation & Steam Generator Blowdown & Sample Isolation Occurred.Caused by Faulty Power Supply to Channel.Power Replaced ML20012B4331990-03-0808 March 1990 LER 90-001-00:on 900206,reactor Tripped as Result of Loop Low Flow Condition Following Trip of Reactor Coolant Pump a, Causing Feedwater Isolation & Auxiliary Feedwater Actuation Signals.Caused by High Differential current.W/900308 Ltr ML20012B4741990-03-0505 March 1990 LER 88-007-01:on 880513,determined That Procedures for Setting Trip Point for Overpower & Overtemp Differential Instrument Loops Did Not Require Setpoints to Be Reset Conservatively.Setpoints recalculated.W/900305 Ltr ML20011D4391989-12-18018 December 1989 LER 89-020-00:on 891117,determined That as-built Configuration of Housing for Both Trains of Containment Cooling Fan HXs Not Seismically Qualified to Withstand Sse. Addl Seismic Restraints installed.W/891218 Ltr ML19332F9111989-12-14014 December 1989 LER 89-021-03:on 881025,preliminary Investigations Indicated That Containment Cooling Fan B Could Not Be Relied on to Perform Intended Design Function.Motor Overcurrent Condition Existed Since installation.W/891214 Ltr ML19325D5261989-10-18018 October 1989 LER 89-019-00:on 890919,determined That No Procedural Problem Existed & Equipment Problem Caused 890915 Test Deficiency.Caused by Reaching Incorrect Conclusion.Train Restored to Svc After Replacement of relay.W/891018 Ltr ML19341D8071988-01-15015 January 1988 LER 87-056-00:on 871215,one 400 Uci Sr-90/Y-90 Source Could Not Be Located.Caused by Inadequate Control of Licensed matl.Fan-Shaped Apparatuses Removed from Svc to Prevent recurrence.W/880115 Ltr 1993-08-03
[Table view] Category:RO)
MONTHYEARML20046C0821993-08-0303 August 1993 LER 93-012-00:on 930510,reported Unusual Noise Due to Small Frictional Force Release in RCS During heat-up.Developed & Implemented Enhanced Thermal Expansion Monitoring Program. W/930803 Ltr ML20045F1451993-06-30030 June 1993 LER 93-011-00:on 930518,nuclear Plant Instrumentation Sys Axial Flux Difference Limits Were Not Updated W/Ts Due to Inadequate Review of Colr.Initiated WR & Computer Software Mod request.W/930630 Ltr ML20044H0751993-06-0202 June 1993 LER 93-010-00:on 930508,Mode 3 Entered from Mode 4 W/Both MDAFWPs Rendered Inoperable by Handswitches Being Placed in pull-to-lock.Caused by Failure to Control Work Activity.Mgt Expectations clarified.W/930602 Ltr ML20045A4931993-06-0101 June 1993 LER 93-009-00:on 930504,noted That Supervising Operator Erroneously Instructed RO to Reset Steamline LP SI Signal Rather than Block SI Signal.Caused by Personnel Error. Personnel Have Been Directed to Review event.W/930601 Ltr ML20044D2821993-05-11011 May 1993 LER 93-007-00:on 930413,determined That Surveillance Test Procedure Re RHR Sys Inservice Pump B Test Not Accomplished by 930410.Caused by Lack of Oversight of Surveillance program.Past-due Notice proceduralized.W/930511 Ltr ML20045H2631992-12-31031 December 1992 LER 92-007-01:on 920326,hot Particle Discovered on Individual Left Cheek.Event Probably Occurred During Use of Plant Communications Equipment.Procedure RPP 02-510 Evaluated ML20045H2701992-04-27027 April 1992 LER 92-007-00:on 920326,hot Particle Picked Up During RCS Shim Restraint Rework Insp Results in Exposure Exceeding 10CFR20.101 Requirements.Hot Particle Control Program & Policies Being reviewed.W/920427 Ltr ML20024G9791991-05-10010 May 1991 LER 90-026-00:on 901123,tech Spec Violation Occurred Re Safety Related Class IE Battery Bank Powered from Spare Battery Charger.Caused by Error in Safety Evaluation for Procedure Mce E051Q-01.Procedure deleted.W/910510 Ltr ML20029B2361991-02-28028 February 1991 LER 91-025-01:on 901223,common Min Flow Path Return Line for SI Pumps to RWST Frozen.Caused by Faulty Ambient Temp Switch.Switches Calibr to Insure Heat Trace Circuits & Alarms activated.W/910228 Ltr ML20029A6481991-02-26026 February 1991 LER 91-002-00:on 910128,essential Svc Water Flow to Containment Cooling Units Below TS 4.6.2.3 Requirements of 4,000 Gpm.Caused by Inaccurate Flow Readings Provided by Local Annubars.Surveillance Procedure revised.W/910226 Ltr ML20028H6901991-01-22022 January 1991 LER 90-025-00:on 901223,determined That Common Min Flow Path Return Line for SI Pumps to Refueling Water Storage Tank Frozen.Cause Undetermined.Need for Effective Communications Will Be Reiterated to Plant personnel.W/910122 Ltr ML20028H4361990-12-28028 December 1990 LER 90-024-00:on 901129,portion of Contents of Waste Gas Decay Tank 6 Discharged While Maint Performed.Caused by Personnel Error.Shift Supervisor counseled.W/901228 Ltr ML20028G9191990-09-26026 September 1990 LER 90-020-00:on 900827,portable Sump Pump Installed W/Pump Discharge Directed to Storm Drains,Bypassing Turbine Bldg Drain Monitor LE-RE-59.Caused by Lack of Communication Between Involved groups.W/900926 Ltr ML20043H7201990-06-18018 June 1990 LER 90-012-00:on 900517,reactor Trip,Main Turbine Trip & Auxiliary Feedwater Actuation Signals Occurred.Caused by Steam Generator C Atmospheric Dump Valve Stuck Open. Converter Positioner Circuitry replaced.W/900618 Ltr ML20043H1531990-06-18018 June 1990 LER 90-013-00:on 900519,main Turbine Trip Occurred as Result of hi-hi Moisture Separator Reheater Level.Root Cause Investigation Not Conclusive.Cautions Added to General Operating Procedure Gen 00-004.W/900618 Ltr ML20043G2761990-06-15015 June 1990 LER 90-010-00:on 900516,discovered That Insp Access Door for Motor Driven Auxiliary Feedwater Pump B Room Cooler Had Been Removed.Caused by Personnel Error.Maint Personnel Informed of Necessity of Doors Being in place.W/900615 Ltr ML20043G0741990-06-13013 June 1990 LER 90-011-00:on 900514,feedwater Isolation Signal & Main Turbine Trip Signal Occurred When Steam Generator B Reached hi-hi Level Setpoint & Generator C Reached lo-lo Setpoint. Caused by Power Oscillations.Procedure revised.W/900613 Ltr ML20043G1991990-06-0808 June 1990 LER 90-007-00:on 900510,feedwater Isolation Signal Occurred Due to Surveillance Test Requiring High Feed Rate.Caused by Feedwater Flow Rate Higher than Steam Flow.Rev to Surveillance Test Procedures clarified.W/900608 Ltr ML20043E9551990-06-0808 June 1990 LER 90-009-00:on 900608,discovered That Circuit Breakers for Accumulator Outlet IV Closed Resulting in Two Inoperable Accumulators.Caused by Personnel Error & Lack of Specific Procedural Direction.Procedure revised.W/900608 Ltr ML20043F1581990-06-0404 June 1990 LER 90-008-00:on 900504,fuel Bldg/Control Room Ventilation Isolation Signals Received from Exhaust Radiation Monitor. Caused by Burned Out Lamp & Blown Fuse in Power Supply.Fuse & Lamp Replaced & Monitor Returned to svc.W/900604 Ltr ML20043A6731990-05-16016 May 1990 LER 90-006-00:on 900416,containment Purge Isolation Signal & Control Room Ventilation Isolation Signal Occurred.Caused by Inadequate Procedures to Govern Deenergization of 120- Volt Ac Distribution Ctrs.Procedures revised.W/900516 Ltr ML20042G9171990-05-10010 May 1990 LER 90-005-00:on 900410,control Bldg/Auxiliary Bldg Pressure Boundary Door Found Open W/O Continuous Watch Established. Caused by Inadequate Procedures.Fire Protection Impairment Control Procedure revised.W/900510 Ltr ML20042G2131990-05-0707 May 1990 LER 90-004-00:on 900405,Tech Spec Surveillance Requirement Not Satisfied Because of Personnel Error in Scheduling Surveillance Test.Procedure Adm 02-300 revised.W/900507 Ltr ML20042E1851990-04-13013 April 1990 LER 90-002-00:on 900314,determined That Halon Release in Either ESF Switchgear Room Would Trip Both Class 1E Electrical Equipment Air Conditioning Units.Caused by Lack of Design Criteria.Criteria revised.W/900413 Ltr ML20043H2871990-04-0909 April 1990 Corrected LER 85-058-01:on 850731,reactor Trip,Main Turbine Trip,Auxiliary Feedwater Actuation,Feedwater Isolation & Steam Generator Blowdown & Sample Isolation Occurred.Caused by Faulty Power Supply to Channel.Power Replaced ML20012B4331990-03-0808 March 1990 LER 90-001-00:on 900206,reactor Tripped as Result of Loop Low Flow Condition Following Trip of Reactor Coolant Pump a, Causing Feedwater Isolation & Auxiliary Feedwater Actuation Signals.Caused by High Differential current.W/900308 Ltr ML20012B4741990-03-0505 March 1990 LER 88-007-01:on 880513,determined That Procedures for Setting Trip Point for Overpower & Overtemp Differential Instrument Loops Did Not Require Setpoints to Be Reset Conservatively.Setpoints recalculated.W/900305 Ltr ML20011D4391989-12-18018 December 1989 LER 89-020-00:on 891117,determined That as-built Configuration of Housing for Both Trains of Containment Cooling Fan HXs Not Seismically Qualified to Withstand Sse. Addl Seismic Restraints installed.W/891218 Ltr ML19332F9111989-12-14014 December 1989 LER 89-021-03:on 881025,preliminary Investigations Indicated That Containment Cooling Fan B Could Not Be Relied on to Perform Intended Design Function.Motor Overcurrent Condition Existed Since installation.W/891214 Ltr ML19325D5261989-10-18018 October 1989 LER 89-019-00:on 890919,determined That No Procedural Problem Existed & Equipment Problem Caused 890915 Test Deficiency.Caused by Reaching Incorrect Conclusion.Train Restored to Svc After Replacement of relay.W/891018 Ltr ML19341D8071988-01-15015 January 1988 LER 87-056-00:on 871215,one 400 Uci Sr-90/Y-90 Source Could Not Be Located.Caused by Inadequate Control of Licensed matl.Fan-Shaped Apparatuses Removed from Svc to Prevent recurrence.W/880115 Ltr 1993-08-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1021999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1071999-04-30030 April 1999 Revised MOR for Apr 1999 for Wolf Creek Generating Station ML20206P8261999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Wcgs.With ML20196L3401999-04-30030 April 1999 Rev 1 to WCGS Cycle 11 Colr ML20210R5841999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Wolf Creek Generating Station ML20205Q0761999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Wolf Creek Generating Station.With ML20207K5991999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Wolf Creek Generating Station.With ML20207K9761998-12-31031 December 1998 Annual SER 14,for Period 980101-1231, for WCGS ML20199E6531998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Wolf Creek Generating Station.With ML20195C0011998-12-31031 December 1998 Ks City Power & Light Co 1998 Annual Rept & Financial Statements as of 981231 & 1997 for Ks Electric Power Cooperative,Inc ML20195B9901998-12-31031 December 1998 Western Resources Annual Rept for 1998 ML20198D7321998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Wolf Creek Generating Station.With ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20195D1791998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Wolf Creek Generating Station.With ML20154L4591998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Wolf Creek Generating Station.With ML20153G2771998-09-30030 September 1998 Rev 1 to WCAP-15079, Wolf Creek Heatup & Cooldown Limit Curves for Normal Operation ML20153G2851998-09-30030 September 1998 Rev 1 to WCAP-15080, Evaluation of Pressurized Thermal Shock for Wolf Creek ML20153G2691998-09-30030 September 1998 Rev 1 to WCAP-15078, Analysis of Capsule V from Wolf Creek Nuclear Operating Corp Wolf Creek Reactor Vessel Radiation Surveillance Program ML20153G7301998-09-23023 September 1998 Special Rept 98-003:on 980814,station Entered TS 3.3.3.6, Action Statment a Due to Inoperability of RVLIS B Train. Cause Has Not Yet Been Identified.Work Order 98-202813-000 Has Been Generated ML20151W1491998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Wcgs.With ML20237B7381998-08-14014 August 1998 Special Rept 98-001:on 980615,oxygen Analyzer on Wgs Was Declared Inoperable.Wgs Oxygen Analyzer OARC-1119A Was Indicating 0 Ppm on 980814 & Fluctuated Between 200 & 900 Ppm on 980615.Completed Work Order & Declared Wgs Operable ML20237B0841998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Wolf Creek Generating Station ML20236P3441998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Wolf Creek Generating Station ML20236P3481998-05-31031 May 1998 Corrected Page of MOR for May 1998 for Wolf Creek Generating Station ML20249A0171998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Wolf Creek Generating Station ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247H0901998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Wolf Creek Generating Station ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20216F6101998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Wolf Creek Generating Station ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20216G1971998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Wolf Creek Nuclear Operating Corp ML20202H0721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Wolf Creek Generating Station ML20217G4311997-12-31031 December 1997 Western Resources 1997 Annual Rept & Financial Statements for Years Ended 971231 & 1996 for Ks Electric Power Cooperative,Inc ML20203H0151997-12-31031 December 1997 Annual Operating Rept 13 for Jan-Dec 1997 ML20217G3711997-12-31031 December 1997 Kansas City Power & Light Co 1997 Annual Rept ML20216D7771997-12-31031 December 1997 Annual SER 12 for Jan-Dec 1997, for Wolf Creek Generating Station 1999-09-30
[Table view] |
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W$LF CREEK NUCLEAR OPERATING CORPORATION - ;
~ John A. Beney
' vieo Preensent i 1
Nucteer Opershons :
l ApM 1 13, 1990 NO 90-0118 ;
U. S.: Nuclear Regulatory Commission i
ATTN: Document Control Desk Hail Station P1-137 -
Washington, D. C. 20555 Subjects Docket No. 50-482:,-Licensee-Event Report 90-002 Gentlemen ,
The attached Licensee Event Report (LER) is submitted-pursuant to 10 CFR -
50.73 (a) (2) (v) as a condition that alone could 'have prevented the fulfillment of a safety function.
Very.'truly yours, L Q. 24 - c John A. Bailey
~Vice President nuclear Operations ,
JAB /jra ,
Attachment cc: R. D. Martin (NRC), w/a D. Persinko (NRC), w/a D. V. Pickett (NRC), w/a M. E. Skow (NRC), w/a l'L 0004200 r,4 soc,4 ; 7 FDF ADOc t. cvfiO O O 4 8
? FDC P.O. Box 411/ Burhngton, KS 66839 / Phone:(316) 3644831 An Equal Opportumty Employer MF/HC/ VET -l
a NRC Feem 306 U 8. NUCLEF KEEUL ATORY COMMI58 TON
, tJM.OYED OMS NO 2160 0104
'"a's 6 23,es
- . LICENSEE EVENT REPORT C ..R) f ACILITY NAME 01 DOCRET NUMBE R t2l PAGE '38 Wolf Creek Generating Station o l5 l0 l0 l0l 4l8 l2 i jorl0 l 4 I (l't'El let Lack Of Design Criteria Leads To Logic In Which Actuation Of A Fire Suppression System Affects Both Trains Of Safety Related Eauipment EVENT Daft 153 LER NUMBER ($1 REPOR Y DAf f (?) OTHER F ActLITit$ INVOLVED 181 MONTH DAf vtAR VEAR 5(Ojy(AL Q( voNiw OAy vgAp f acitet y N AMES DOCK E T NUM9t Al5i 015l0l0(o[ g l
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0l3 1l 4 9 0 9 l0 O l 0l 2 0l 0 l l l 0 l5 1 0 1 0 io; l l THIS REPORT iS SUSMITYtD PURSUANT 70 THE REOutREMENTS OF 10 CPR g IC4ece esse or more of rae favoems1 OH OetRATING MOOf m 5 ,,,,,,,, ,,,,,,,, .,,,, a, n,, ,,,,,,,
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20 406teHilb661 60.73 eH2Hil 60,73teH2HvihHAl J664) to 406leiHHal 50.73te H2HM 50.73 eH2Hvi6611BI 20 406telt1 Hut 60.736s H2Huil 50,7LeH2Hal LICENT.E t CONT ACT FOR THIS LE R (121 NAME TE LEPHONE NUMBER ARE A CODE Merlin G. Williams - Manager Plant Support 33;6 36,4, ,8,8 i 3;1 i
COMPLETE ONE LINE FOR E ACH COMPONENT F AILUR8 DESCRIBtD 44 TH18 REPORT H31 M^ C M' C OnfA Lt CAUSE SYSTEM COvPONENT E tO N8 DS CAUSE sv8 TEM COMPONENT pg g i I I I I I I I I I I I ! I l l l I l l 1 i l I i l I l EUPPLEMENTAL REPORY EXPECTIO (141 MONTH DAY VEAR SUSWSSION NES Uf ves. tometere (KPECVCO $Ugw$$10N CATli NO l l tSSTR ACT ILamut to 9400 sones o e , sooroveete'y Mreen smg'e soece troewertron knev 0et on March 14, 1990, following a discussion with personnel frm another utility, it was determLned that a Halon release in either Engineered Safety i Features (ESP) Switchgear Rom would trip both Class lE Electrical Bguipnent Air Conditioning Units. As an initial corrective action, the affected Halon release circuits were disabled and a fire watch was established for both ESF Switchgear Rocas. A permanent design change has been developed to alter the circuitry such that only the associated Air Conditioning Unit will be j secured in the event of a Halon release.
The root cause of this event was the lack of design criteria to clarify the train separation requiremnts of nonsafety related/special scope logic signals which actuate multiple trains of safety related equipnent. 'Ihe design criteria have been revised to include these requiranents. A review has been conducted of all circuitry potentially affected by this lack of design criteria. No additional design deficiencies were identified during the review.
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IXPIRES 4/3092 LICENSEE EVENT REPORT (LER) f,Un,',"o',y"8'l's",o"'!En,'%Cf7'.' nin"J"'s ;
TEXT CONTINUATION !"J"n'.",'o'"!'u'"OjMf!We'U,'!d '".'OcTf! ;
OMi%"Jo!?"*i!'JEM',!EEE1Es*oEE Wei or uAwAosutw1 ANo evoost virassinoToN.oc 20603, j racitiiv name m oocati Nuussa tai ten unusen te, paos isi . .
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Wolf Creek Generating Station o l5 l0 l0 l0 l4 l8 l 2 9l0 -
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L IND G UCTIOi On March 14,1990, following a discussion with personnel fran another _
utility, it was determined that a Halon release in either Engineered Safety Features (ESF) Switchgear [JE] Rom would trip both Class lE Electrical Equipnent Air Cor ditioning Units [NA-ACU). As an initial corrective action, the affected Halon release circuits.were disabled and a fire watch was established for both ESF Switchgear Ro ms. his condition is being mysted 7 pursuant to 10CER50.73(a)(2)(v) as a cmdition that alone could have ;
prevented the fulfillment of a safety function. ,
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i DESC3tIPTION OF EVENT t l
r On March 14, 1990, during a conversation with personnel fr m another utility, Wolf Creek Nuclear Operating Corporation (NCNOC) engineering ;
personnel were notified of a potential design deficiency in that actuation 4 of the Halon Fire Suppression Systan in one ESF Switchgear Rom would trip the Class 1E Electrical Equipment Air Conditioning Units in both ESF.
Switchgear Roms. NCNOC engineering personnel subsequently corifW that the condition also existed at Wolf Creek Generating Station.. Per design documentation, one Halon release auxiliary relay contact fran each ESF '
Switchgear Room was wired to each of. the Class 1E Electrical Equipnent Air Conditioning Units auxiliary relays. mis wiring configuration would have resulted in a shutdown of both Air Conditioning Units in the event of actuation of the Halon Fire Suppression System in either of the~ESF ,
Switchgear Roms. Furthentore, this logic would. override the Class 1E Electrical Equignent Air Conditioning Units start signal that would be initiated by a Control Rom Ventilation Isolation Signal or a Ioad Shed/ Emergency Ioad Sequencer Actuation Signal.
At the time of this discovery, the unit was in Mode 5, Cold Shutdown. At approximately 1638 CST, the Halon Fire Suppression System Controls for both ESF Switchgear Ro ms were placed in inhibit and firewatches were established for the affected areas in accordance with administrative procedures. -As a i long term corrective action, a permanent plant nodification has been developed to make wiring changes to the Halon shutdown contacts. We wiring change will allow for a'Halon Fire Suppression System actuation to trip only the Class lE Air Conditioning Unit for the affected ESF Switchgear Room.
Following implemantation of this design change, the Halon control circuitry will be restored to operation. <
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'Ihe root cause of this situation was the lack of stated design criteria to clarify the train separation of nonsafety related/special scope logic signals which actuate the logic for mitiple trains of safety related equipnant. h design basis requirunent for isolation of the class lE Electrical Equipnent Air Conditioning Units was to ensure proper ESF Switchgear Rom Halm canoentraticn. 'Ihis requirunant was satisfied by wiring one auxiliary relay contact from each of the ESF Switchgear Ro m Halon release circuits to each Class 1E Electrical Equipnent Air Ccoditioning Unit. In the design of the Halon release circuit, the physical and electrical separation requirunents were met, but there was no design requixanent to check the circuit logic to confirm that there was no adverine train interaction. It was determined that the only affected circuits were those in which a safety related circuit would be actuated from a ncesafety related/special scope logic signal through an isolation device.
WCNOC engineering personnel have reviewed the schenatic diagrams and logic diagrams of all the auxiliary relays used as isolation devices. As a result of this review, it was ocncluded that no other similar design deficiencies exist at Wolf Creek Generating Station.
In order to prevent future occurrences of this nature, the design criteria have been revised to include a statement that system logic between nonsafety '
related/special scope circuits and safety related circuits mast be configured to prevent adverse actuations of multiple trains of safety related equipnant.
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l ADDITIGE IMGMhTIQ(
L h safety related function of the Class 1E Electrical Bauipnent Air
- Conditioning Units is to operate in a continuous recirculation node to maintain the ESF Switchgear room, the battery rooms, and the DC Switchgear
- roms at or below the design taperature. While the refrigeration subsysten is in operation, the anount of cooling provided is self-regulated by the Air l Conditioning Unit control circuit. 'Ihe principal control functions are provided by a taperature switch / step controller which autmatically starts and stops the Air Conditioning Units as required. Indicaticn of a loss of preferred AC power, or a loss-of-coolant accident will autmatically <
l initiate the Class 1E Electrical Equipment Air Conditioning System if not-already in operation. However, the design function of this system was overridden by a Halon release in either of the ESF switchgear roms, associated battery rooms, or associated DC switchgear roms. By making the Nae ,- mm...
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0l012 l- 010 014 oF 0l4 vio,, . ,. .c, - wim wiring changes, the syntan will then be designed par the original operational intent and thus cnly the Air Conditioning Uni'c associated with the rocan in which a Halon release has occurred will be stopped.
An evaluation of the consequences of a fire or a false actuation in one of the ESF Switchgear Rooms has determined that no significant adverse offacts would have occurred to prevent the mitigation of an event. Although both Air Conditioning Units would have been removed fran service, once the fire had been extinguished, the Halon systan would be reset per p.vcidure. By resetting the Halcn Systan, both Air Corditioning thits would be returned to service.
'1here have beeng previous similar occurrer.m.
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