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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] |
Text
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VU$LF CREEK 1 '
NUCLEAR OPERATING CORPORATKW John A. neuer '
v=e m -December 14, 1989 i 88uesaw oseressas NO 89-0216 'l l
U. S. Nuclear Regulatory Commission ATTN Document-Control-Desk
,3E Mail Station P1-137 )
_ Washington..D. C. 20555 E
Subjects Docket No. 50-482: Licensee Event Report 88-021-03 ;
Gentlemen:
i
\
The attached Licensee Event Report (LER). provides a supplement _ to LER 88 021-02. _This event was originally reported pursuant- to ?
10 CFR 50.73(a)(2)(1)(B) as a condition prohibited by Wolf Creek Generating .j Station (WCGS) Technical Specifications. This . supplement provides the j results of evaluation of the potential-.cvercurrent condition on a Containment- Cooling Fan Motor. 'the evaluation identified that the motor _ ';
.would have been able to perform its' dvidgn ' function under normal'.and accident conditions. Subsequently. Wolf Creek Nuclear Operating Corporation-chas. concluded that no condition prohibited by WCGS Technical Specifications existed.
Very truly yours.
y p , d -
John A. Bailey Vice President Nuclear Operations JAB /aem
' Attachment r
cc D. L. Bartlett.(NRC), w/a E. J. Holler (NRC), w/a R. D. Martin (NRC), w/a D. V. Pickett (NRC), w/a 8*12190301 891;14 F'DR ADOCN 05000482 S p pc P.O. Box 411/ Burhngton, KS 66839 / Phone: (316) 364 9831 2 k l
+
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ashC 9e,m att U 6. NUCL LQQ C.tCULOTDJU CCMMI5600N 1 A?PMOVED Out NO 3100M.8 LICENSEE EVENT REPORT (LER) ( ""a' 5 ' '8'
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Wolf Creek Generating Station 0 l 5 l 0 l 0 l 014 l 8] 2 1 lod 0l7 l
"' Supplemental Report Describing Final Evaluation Of Containment Cooling Pan Motor I Potential Overcurrent Condition tVtNT DATI 16) Lt A NUM.E m del atPORT DAf t th OTHE R P ACILifit t INVOLVE D (5)
MDN7M DAY YEAR Y E Af1 g', ' 4 M'[j$ MONTw oat VI apt . ACILeT V hawt$ DOCKS T NUM0t p4Si 016101010 1 I i
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,1 I I I I I I I I I I I ! l SUP*LlutNT AL REPORT G RPECit D H.I MONTH DAY YEAR SUSMISSION YES V,y .em,w.
' lkPECilD SU$4,IS$f0N OA til NO l l l AuTaACT , hm-....,,,,..-.,,,,-,.,..,,,n., l l
On October 25, 1988, at approxinately 1600 CETT, as a follow-up to canditions !
identified during Integrated leak Rate Testing (IIRT), preliminary investigations indicated that Containment Cooling Ita 'B' could not be relied upon to perfom its intended design function under accident conditions due to a notor overcurrent condition. Containnent Cooling Fan
'B' was declared inoperable.
At the tim, it appeared that the notor overcurrent condition had existed l E
since the mtor was initially installed on July 25, 1987, (i.e. the
). condition did not appear to be due to notor degradation). Due to l
- 1. . inconsistencies between actual notar perfomance during the IIRT and the vendor-supplied notor test report, it was celleved the notar could not be l
- t. relied upon to perfom its design function under accideat conditions. 'Ihe L
notor was replaced with a qualified notor.
'Ihis supp1 ment is being issued to detail the final results of the
- evaluations conducted in conjunction with the vendor. These evaluations l-concluded that the notar would have been able to perform its design functica l
i under normal as well as under accident conditions, i.ti,'"" *"
0 IfRC ,orm s.6A U.S NUCLE A3 f.419Lt. TORY COMMthel04 UCENSEE EVENT REPORT (LER) TEXT CONTINUATION APrRoe owe no oso-m EXP RES l'8088 9 AC8ktiv hAME Of DOChli NUM88M G8 Llm NUMBER 16p PA04 (3) vlaa " RM O.*,T Wolf Creek Generating Station o l6 j o j o l 0 l 4l 8l2 81 8 0l2l1 -
0l3 Q2 oF 0 l7 rm . e o . - w , amuwnn INBGUCFICBI On October 25, 1988, at approxistely 1600 CDP, as a follow-up to conditions idetified during Integrated leak Rate Testing (IIRT), preliminary investigations indicated that Contalment Cooling Fan 'B' [BK-FAN) could not be relied upon to perfoon its intended design function under accident conditions due to a notar overcurrent condition. Containment Cooling Fan
'B' was declared inoperable. Subsequent evaluation concluded that this condition had existed since the notor [BK-)O) was initially installed on July 25,1987. Following the installation of this notor, the plant had l operated in all nodes. Technical Specification (T/S) 3.6.2.3, applicable for lede 1, Power Operations, through Mode 4, Hot Shutdown, requires two independent groups of Contalment Cooling Fans to be operable with two fan systems to each group. With one group inoperable and both Containment Spray Systems (BE) operable, T/S 3.6.2.3, action statement 'a', requires restoring the inoperable group of cooling fans to operable status within 7 days or being in at least }bde 3, Hot Standby, within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in Mode 5, Cold Shutdown, within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. In addition, T/S 3.0.4 prohibits entry into an operational node or other specified condition unless the conditicms for the Limiting Candition for Operation are net without reliance on the provisions ccntained in the action requirsents. Therefore, this event was originally reported pursuant 10CFR 50.73 (a)(2)(1)(B) as a condition prohibited by the plant's T/S.
mis su @lement is being issued to detail the final results of the evaluations conducted in conjunction with the vendor. %ese evaluations concluded that the notar would have been able to perform its design function under nomal as well as under accident conditions. Consequently, no condition prohibited by the plant's T/S ever existed.
DESCRIPTI(N OF (RIGURL BV12ffS On July 20, 1987, at approximately 1149 CDP, Containment Cooling Fan 'B' tripped. We plant was in Mode 1, with the Reactor (AB-RCT) at approxistely 100 percent power. Containment Cooling Fan 'B' was declared inoperable and T/S 3.6.2.3, action statment 'a' was entered. ,
4 On July 20, 1987, at approximately 2303 CDP, the plant experienced a Reactor Trip as discussed in Licensee Event Report (LER) 87-030-00. The Reactor Trip was neither caused by nor affected by the inoperable Containment Cooling Fan. However, T/S 3.0.4 prohibited entry into !bde 2, Startup, with Contalianent Cooling Fan 'B' inoperable.
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0] 3 0l3 OF 0l 7 f tKT (J pere spece de agpeet s#se semesist MIC Fenn JUEA W 1171 l Subsequent inspection of Containment Cooling Fan 'B' revealed that one of l the sixteen variable pitch fan blades had failed damtging several other fan blades. W e damaged fan blades were replaced. %c three runninirq Containment Cooling Fans were inspected to verify that the fan blades were firmly fastenad, at the correct pitch, and that there was no excessive notor vibration. his informatim indicated that the fan blade failure was an isolated event, not indicative of a generic design or manufacturing error that would result in the simultaneous failure of the other Containment Coolby Fans.
Examination of the fan motor identified that the notor shaft had excessive runout which indicated a possible bearing failure. mis fan notor was replaced with a new assembly on July 25, 1987. Following motor installation, notar current amperage readings were measured and recorded.
These readings were within the nameplate ratings for the notor. After Containment Cooling Fan 'B' was restored to operable status, the plant I entered Mode 2 on July 26, 1987, at approximately 0515 CDP, and Mode 1 at appmdmately 0740 CDP.
On October 17, 1988, while pressurizing Containment [NH] for the IIRr, Containment Cooling Fan 'B' was taken off line due to current values in excess of the notor's nameplate rating. % e fan was restarted when Containment was at a pressure of 50.4 psig, at which time Cmtainment Cooling Fan 'B' drew 164 anperes in slow speed. % e fan was again taken off line and a request for an engineering evaluation was initiated. % e plant was in Mode 5 in preparation for the third refueling at the time of the
- nRr.
On October 25, 1988, at approximately 1600 Ctrr, preliminary investigations by Engineering indicated that Containment Cooling Fan 'B' could not be relied upon to perform its intended design function under accident conditions. No-load testing was then conducted to determine if the l described condition was the result of fan or motor problans. W e no-load ,
test results were as follows: !
i i
Fast Speed (1200 rpn) Slow Speed (600 rpn)
Current Current
-Phase A 64 anperes Phase A 142 amperes Phase B 65.2 anperes Phase B 140 anperes Phase C 65.9 apperes Phase C 140 anperes l
l Based on the performance data supplied by the manufacturer with the original fan notors, the no-1 cad motor current should be approximately 41 and 104 amperes for fast and slow speed, respectively. l J
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WRC form antA U S ECUCLE A3 etttVLATOlY COMuttstot UCENSEE EVENT REPORT (LER) TEXT CONTINUATION eeaovto oMe wo mo-cine EXPlRf18'31'te t csL81Y HAM 4 Hi 00CR47 NUMet h (28 LtRNUMeth(6) PAGE (31 m- "empt' nm Wolf Creek Generating station o p;ojojol4;8;2- ej 8 _ 0;2l1 _ 0;3 0 ; 4 lo, 0;7 im <n . .- a*c ,,,,, m., m, As a result of a rwiew of all data taken during the events of July,1987, and a ocmparison with the data rw.=44 during IIRT, it agpeared that the notor overcurrent condition had existed since the notor as initially installed on July 25, 1987, (i.e. the condition did not appear to be due to notor degradation).
N nameplate values given on the notor test report supplied by the verdor with the notor met the design specifications for the notor. However, the l values for the no-load and nansplate ratings on this notcr test report '
appeared to be inconsistent with each other. h no-load value of 129.6 anperes on the test mport appeared to be too high to meet the full-load i nameplate rating of 147 anperes. Table 1 (attached) provides a ocmpilation of notor current data. In addition, the actual notor performance as naasured during the IIRT ms inconsistent with the notor test full-load value. Uhe actual fan notar current values measured during these tests exceeded the nansplate current values.
Due to these inconsistencies, it was believed the notor could not be relied upon to perfozm its design function under accident conditions. 'Ihe notor was replaced with a qualified notor. Paview of the notar test reports and field tests for other fan-notors in this application did not idantify ,
additional inconsistencies of this type. h refore, it was believed that this was an isolated case.
I ruar muarra h subject notor was returned to the supplier for testing in accordance with the original purchase specification. Wolf Creek Nuclear Operating Cwgudtion (WCNOC) engineering personnel were present to witness this testing and to discuss the identified problem with the notor nunnfacturer.
A preliminary test report documenting the ccmplete results of the above tests and an evaluation of these results has been ptwided to NOOC by the supplier, h conclusion of the preliminary test report indicates that the subject notar has passed all tests required to ensure the notor will meet the application requiranents. However, this notor has a lower power factor at 1cw speed than notom of the sane design which results in notor full-load current greater than the naneplate value.
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=ac e.. ma v s evettu motaTony commits o= I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ***aovie oMi womo-om
. EXPihES 4'312
- 9 ACILeiv 4Amt Of DOCkti NUMS$R CH Lt h WUMBt h ($6 PACE (31 nsa " t%" .
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Wolf Creek Generating Station o p ;o yolo; 4;8 g2 8; 8 _ 0; 2 l1 _ 0;3 05g or 0 j7 TLKT I2 mee apete h retood, see es@noner MC Fem Jn6A M 41D NWOC engineering i=.cnnel have reviewed the additional informaticn submitted by the supplier. Based upon this review, it was determined that the notor would meet the requirments for the particular application (i.e.
brake horsepower, torque, tenparature rise, etc. ). However, it was necessary to ensure that the additional full-load current would not impact the notor overcurrent protection. A calculation was performed to ensure that the notor would not trip on thermal overload when required to mitigate the consequences of an accident. In addition, it was determined by this calculation that the existing thermal overload heaters are sized properly for use with the subject notor. The locked rotor current determined by test for this notor is essentially the sane as that for the original notors at both speeds. 'Iherefore, the existing instantaneous overcurrent settings will not trip the notor during acceleration.
'Iherefore, it has been determined that the Cantainment Cooling Fan notor ruoved frun service curing October of 1988 could have been relied upon to ,
mitigate the consequences of an accident. 'Ihis motor will draw higher !
current at full-load and no-load due to its lower power factor. However, I the existing overcurrent protection is sized am usiately for use with this
-notor. It has therefore been determined that tw.re is no technical proble associated with the subject notor.
As a result of a surveillance perfomed of the notor manufacturer and a revic.; of Wolf Creek Nuclear Operating Corporation's (NCNOC) acceptance program, deficiencies were noted. - As identified, the notor condition was the result of the subject notar having a lower power factor in slow speed than other notors of the same design. Both hCNOC and the supplier failed to identify this motor discrepancy. The supplier's quality assurance swmn did not require documentation of deviations frm naninal test values and evaluations of such deviations. Consequently, these evaluations were not available to NCNOC. Upon receipt of the notor, the routine notor test report was not reviewed by NCNOC engineering personnel as a supplier subnittal. 'Iherefore, the notor was received and installed without identification and subsequent evaluation of the discrepancy.
i
'Ib prevent recurrence, the Supplier Information List and the NCNOC materials l management dauhue will be revised to invoke purchase order requirments 1 for all future safety related replacement motor purchases to ensure that routine notor test reports are subnitted to NCNOC and that any routine notor deviaticns are identified, evaluated, h-ited and subnitted for approval prior to release of the notor for shipnent. 'Ihese revisions will be ccupleted by February 28, 1990. NCN3C procedures will be reviewed and revised as necessary to ensure that supplier subnittals are forwarded to pg ppg gg 8 '$.
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ExP'nts. t'31 '88 f ACILITY hAMt (11 DOCK E T NUMtt h (U L(R NUMSIR 44) PAGE (Si visa "20!?!'.'. ' -O'J'.'O Wolf Creek Generating Station 0 l6 l0 l0 l0 l4 l 8l 2 8l 8 -
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0l3 0 l6 0F 0 l7 TtKT (2 mwe appre 4 meurest sese emmener MC form 316Caltth engineering for review and acceptance prior to release of the material for installation. 'Ihese gvcx,-lural revisions will be ocmpleted by February 28, 1990. As a remedial action, the routine motor test reports for safety related continuous-duty replacement notors received frun this manufacturer since the time of cannercial operation will be reviewed against the routine notor test reports for the original notors to ensure motor characteristics are within notor overcurrent design. 'Ihis review will be ocmpleted by - .
February 28, 1990. i The Cbntainment Cooling Fan notar is manufactured by Reliance Electric i Capany, part number 600287-43. The notor is a 460 volt two speed notor (rated at 150/75 horsepower).
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'Duble 1 Nttor Cmzutt Data l l
S[W SPEIO (600 rps) i (AcMrheit mda of Operation) ;
1 NEMILRED M3KR NhMEPUEE MFKR TEST REKRT IIRP E IOhD (full-load) Ino-load) 147 129.6 164 Phase A 142 Phase B 140 .
Phase C 140
, i FASP SPEED (1200 qun)
(Routine m de of Operation) unastRio MMR NhMEPUEE M71TR TEST RERRT IIRP W IDhD (full-load) (no-load) 167 58.8
- Phase A 64 Phase B 65.2 Phase C 65.9 Not Applicable I
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