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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
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W4pLF CREEK NUCLEAR OPERATING CORPORATION Otto L. Maynard Vice President Piant Operations May 11, 1993 WO 93-0100 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station F1-137 Washington, D. C. 20555
Subject:
Docket No. 50-482: Licensee Event Report 93-007-00 Gentlemen:
The attached Lice:'see Event Report (LER) is being submitted pursuant to 10 CFR 50.73 (a) (2) (1) (B) concerning a Technical Specification violation.
Very truly yours, O
[
Otto-L. Maynard Vice President Plant Operations OLM/jan cc: W. D. Johnson (NRC) , w/a J. L. Milhoan (HRC), w/a ,
G. A. Pick ( NRC ) ', w/a >
W. D. Beckley (NRC), w/a I t
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LICENSEE EVENT REPORT (LER) f aC)Liiv NAME 11) DOCEE Y NUMBE R (2) FA0E '38 Wolf Creek Generating Station o 1510101 o l41812 1 lorl 016 l
""' Late Surveillance Test Performance Caused By Lack Of Oversight Of The Surveillance Program Results In A Technical Specification Violation EVEhT DATE 151 LE R NUMBE R d66 SEPORY DATE (71 OTHE R 5 ACILtTtI S INVOLVE D 18p N pay g g as; s aOtti v %Avi s pg( K E T Nyygsg R-p
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ABSTR ACT 4 ref te 7430 speces e e . ecero.< mere + 84reca s<ap e spece r.pewnreen uness 0 61 Or, April 13, 1993, at approximately 1715 CDT, it was determined that f surveillance test procedure STS EJ-100B, " Residual Heat Removal System )
Inservice Pump B Test," had not been accomplished by April 10, 1993. ]
This surveillance test is required to be performed on a quarterly basis per Technical Specification 4.0.5 to demonstrate operability of Residual Heat Removal Pump (RHR) "B". On April 14, 1993, at 0010 CDT, RHR Pump ,
"B" was declared operable following the successful performance of !
surveillance test procedure STS EJ-100B.
The root cause of this event was a lack of oversight of the Surveillance j Program. After it was identified that STS EJ-100B had the potential for becoming late, an attempt to resolve the deficiencies was not performed in accordance with step 6.6.2.5.1.2 of Administrative Procedure ADM 02-300. Corrective actions include the proceduralization of the use of a Past Due Notification Sheet, which will be routed to the Control Room when a surveillance test procedure has not been completed at least two days prior to its late date. This will eliminate the use of verbal communications to relay information regarding surveillances becoming late and will place the Control Room in the information loop.
NRC term 366 19 63)
C FDCI3 386A US WUCLEAR REGULATORY COMMISSIOCW E MPIRES 4?30'97 -
LICENSEE EVENT REPORT (LER) 'Sgad', o',""E&t'c'"o"'!*%*,$E,T C P,v s Df
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T PAPE RWD REDu TION JC d 50 04 O OF MANAGE MLNT AhD SUDGEt, WASHINGTON.DC 20603, f aC8LETY 4AME IU DOCE1T WUMBER (2) EER WUMBER 16) PAGE (31
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Wolf Creek Generating Station o p l0 lo j o l41812 9l3 -
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0l0 0l2 Or 0l6 nn -. -- - ~>c w., m, PLANT CONDITIONS AT TIME OF DISCOVERY Mode 6, Refueling Reactor Coolant System Pressure - O pounds per square inch gauge Reactor Coolant System Temperature - less than 100 degrees Fahrenheit Reactor Coolant System Level - Approximately 15 inches below the Reactor Vessel Flange with the Reactor Head set and three studs tensioned l, i
BASIS FOR REPORTABILITY l l
On April 13, 1993, at approximately 1715 CDT, it was determined that i surveillance test procedure STS EJ-100B, " Residual Heat Removal System f Inservice Pump B Test," had not been accomplished by April 10, 1993. }
This surveillance test is required to be performed on a quarterly basis [
per Technical Specification 4.0.5 to demonstrate operability of Residual {
Heat Removal Pump (RHR) "B" [BP-P). The failure to perform surveillance !
test procedure STS EJ-100B within the required time-frame is being i reported pursuant to 10 CFR 50.73 (a) (2) (i) (B) as a condition prohibited f by the plant's Technical Specifications. j i
DESCRIPTION OF EVENT t
Technical Specification 4.0.5 requires, in part, that inservice testing of ASME Code Class 1, 2, and 3 pumps and valves be performed in !
accordance with Section XI of the ASME Boiler and Pressure vessel Code l and applicable Addenda. The Technical Specification further states that l each surveillance requirement must be performed within the specified ,
surveillance interval with a maximum allowable extension not to exceed '
25 percent of the stated surveillance interval. l In accordance with the requirements of Technical Specification 4.0.5, i surveillance test procedure STS EJ-100B, "Pesidual Heat Removal System j Inservice Pump B Test," had an assigned due date of March 18, 1993, at l 1510 CST, with a late date of April 10, 1993, at 1510 CDT. On March 13, 1993, RHR Pump "B" was declared inoperable in order to perform required non-pump related maintenance during the Sixth Refueling Outage. Since the pump was out-of-service, the performance of the surveillance test ,
procedure was not scheduled on the Control Room R1 Status Chart. The R1 l Status Chart is used by Control Room personnel to track required i surveillances that are performed on a monthly or longer frequency. ,
Surveillances which are scheduled for equipment that is out-of-service !
were removed from the Control Room R1 Status Chart for this refueling outage to prevent confusion with surveillances that are required to be performed on operable equipment. l l
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010 013 016 Tl'KT 191 mn, noect M renumnf., us,00$toonet kMC Form 36fA sI(111 on April 6, 1993, during a routine review of the R1 schedule, which is maintained by the Surveillance Group, the Surveillance Coordinator noted that surveillance test procedure STS EJ-100B had the potential for not being accomplished by the required date. Step 6.6.2.5.1.2 of Administrative Procedure ADM 02-300, " Surveillance Testing," requires the Surveillance Group to routinely review the R1 schedule to identify any scheduled R1 surveillances which have the potential for being missed. It also requires an investigation to be performed to determine the status of any R1 surveillances meeting this criteria, and if the defi ciencies cannot be readily resolved it shall be brought to the ,
attention of Plant Management for resolution. Following discovery of the condition on April 6, 1993, the Surveillance Coordinator verbally discussed the potential for STS EJ-100B becoming late with Operations t Supervision. Also, on April 8, 1993, operations Supervision was verbally informed of the condition. The requirement for the performance ,
of the surveillance was placed on a maintenance work schedule following the discussion, but this schedule is not used by the Control Room for surveillance activities. However, Operations Management did not follow- '
up the concern with the Control Room because it was believed that the situation was being addressed by the Surveillance Group and the requirement to perform the surveillance test would be put on the Control ,
Room R1 Status Chart for completion. On April 8, 1993, RHR Pump "B" was returned to operable status following repairs to RHR Pump Room Cooler SGL10B [BP-CLR]. ,
on April 13, 1993, questions were raised by an Outage Management Representative concerning when surveillance test procedure STS EJ-100B would be accomplished. Following an investigation, the manual surveillanca testing tracking log, which is maintained by the Survei31ance Group, was consulted and it was determined that STS EJ-100B had not been acccmplished by April 10, 1993, as required by Technical !
Specification 4.0.5. At 1715 CDT, the Shift Supervisor was notified of ;
the necessity to perform surveillance test procedure STS EJ-100B. Upon being notified that the surveillance had been missed, the Shift Supervisor declared RHR Pump "B" inoperable and entered Technical Specification 3.9.8.2. Technical Specification 3.9.8.2 requires, in part, that with less than two independent residual heat removal loops operable while in Mode 6 with the water level above the top of the reactor vessel flange less than 23 feet, immediate corrective actions must be initiated to return the required RHR loop to operable status, or i establish greater than or equal to 23 feet of water above the reactor vessel flange, as soon as possible. At 1740 CDT, performance of surveillance test procedure STS EJ-100B was commenced to verify l operability of RHR Pump "B". On April 14, 1993, at 0010 CDT, RHR Pump "B" was declared operable following the successful performance of surveillance test procedure STS EJ-100B and Technical Specification 3.9.8.2 was exited.
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ROOT CAUSE The root cause of this event was a lack of oversight of the Surveillance Program. After it was identified that STS EJ-100B had the potential for beccming late, an attempt to resolve the deficiency was not performed in accordance with step 6.6.2.5.1.2 of Administrative Procedure ADM 02-300.
Operations Management was informed of the potential for STS EJ-100B to be late; however, believing that the Surveillance Group had control of the situation, Operations Management did not follow-up on this concern with the Control Room. The Surveillance Group did not follow-up with the Control Room to ensure that STS EJ-100B would be accomplished within the time requirements of Technical Specification 4.0.5.
CONTRIBUTING FACTORS ,
- 1. Failure to have surveillance test procedure STS EJ-100B on Control Room R1 Status Chart.
- 2. Use of multiple schedules for the accomplishment of tracking of surveillance test procedures.
- 3. Lack of adequate procedural guidance on the performance of investigation and follow-up required to correct deficiencies identified for potential late surveillances.
CORRECTIVE ACTIONS In response to this event and previous events involving late performances of surveillance test procedures, Administrative Procedure ADM 02-300 is being superseded by procedure ADM 01-300. The rewrite of ;
the procedure is based on continued input from other plants and knowledge gained from late performances of surveillance test procedures in the past. This rewrite will proceduralize the use of a Past Due Notification Sheet, which will be routed to the Control Room when a surveillance test procedure has not been completed at least two days prior to its late date. This will eliminate the use of verbal communications to relay information regarding surveillances becoming late and will place the Control Room in the information loop. Procedure ADM 01-300 will be issued by June 30, 1993.
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T w w , , - . .,,- .nr.ac w w . , <,T, The use of multiple schedules to track surveillance test procedures is currently being evaluated to determine if the use of one schedule would be appropriate to eliminate confusion. If it is determined that the use i of one schedule is warranted based on the results of the evaluation, the use of one schedule will be implemented by December 6, 1993. l SAFETY ANALYSIS During the time that RHR Pump "B" was considered to be inoperable due to the failure to perform STS EJ-100B IApril 10, 1993, at 1510 to April 14, 1993, at 0010 CDT) the pump was fully functional. Also, the ;
satisfactory completion of the surveillance test procedure on April 14, 1993 indicates that the pump would have performed its required safety function had it been needed. Therefore, the health and safety of the .
public and plant safety was assured during this condition.
f PREVIOUS SIMILAR OCCURRENCES Licensee Event Report (LER) 482/87-014-00 discusses an event in which '
the completion date was incorrectly entered into the Surveillance procedure scheduling program by nonlicensed operations personnel which resulted in the calculation of an incorrect due date for the next performance of the surveillance test procedure. Corrective actions for that event included the checking of the past due Surveillance Procedures Inquiry every week and building checks into the computer program to question the date entered if it is not within a specific range of the current date.
LER 482/90-004-00 discusses an event in which a scheduled surveillance '
test was not performed because of a scheduling error. The performance ;
date of a surveillance was not entered in the computerized surveillance tracking system and consequently no new "due date" for the surveillance j was calculated. Corrective actions for that event included proceduralizing a requirement to check the Past Due Surveillance Inquiry Report on a weekly basis. The event discussed in this report was initially identified by a review of the Past Due Surveillance Inquiry Report. However, when the condition was identified, personnel relied on the control Room R1 Status Chart to indicate that the surveillance had been performed.
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010 Ol6 M 016 nrTur-.-. ,,- -C, .-.e LER 482/91-009-00 discusses an event in which a scheduled surveillance ;
test was not performed prior to restoring a piece of equipment to operable status. That event was attributed to a lack of interface between the Equipment Out-of-Service Log and the Surveillance Testing
- Program. Corrective actions discussed in that event are not applicable ,
to this event.
f LER 482/91-011-01 discusses an event in which the control Room R1 Status Chart was improperly marked to indicate ccmpletion of a surveillance test after only a partial performance of the surveillance test had been ,
acecmplished. Corrective actions for that event included adding step '!
6.6.2.5.1.2 to procedure ADM 02-300, which as discussed previously, j requires an investigation to be performed to determine the status of any R1 surveillance which has the potential for being missed, and if the de fi ciencies cannot be readily resolved it shall be brought to the attention of Plant Management for resolution. The corrective actions
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discussed in this report, including the use of the Past Due Notification Sheet, will ensure that discrepancies identified by the Surveillance Group receive adequate resolution.
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