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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
-M - ~- .,a 4 .a - 4-.n a a a+w'- -u-- 2-ese Wl$LF CREEK NUCLEAR OPERATING CORPORATION
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l May 10, 1990 NO 90 0147 U. S. Nuclear Regulatory Conmission ATTN Document Control Desk '
Mail Station P1-157 Vanhington, D. C. 20555 Subject Docket No. 50-482: Licensee Event Report 90-005-00 Gentlemen The attached Licensee Event Report (LER) is being submitted pursuant to ,
10 CFR 50.75 (a) (2) (i) _ as a Technical Specification violation and 10 CFR 50.75 (a) (2) (ii) a condition that was outside the design basis of the plant. >
Very truly yours,
% O . A4-John A. Bailey ,'
t Vice President Nuclear Operations .
JAB /jra j Attachment L cc R. D. Martin (NRC), w/a l D. Persinko (NRC), w/a .
l D. V. Pickett (NRC), w/a M. E. Skow (NRC), w/a f
9005160281 T OM,10 FDR ADOCL 096694g;.
F DL P.O. Box 411/ Burhngton. KS 66839 / Phone: (316) 364 8831 An Equal opperuWy EW Mf/HGYET ,
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. APPPOVt0 Out NO *lt0010s LICENSEE EVENT REPORT (LER) 8 "R t * ' '8*
. ACILITY NAMI 11) DOCKt1 NL,M9t h (Il PaGE 63 Wolf Creek Generating Station _
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"'' Improper Control 01 Pressure Boundary Doors Caused by Inadequate Procedures Adversely Ef f ects Control Room Energency Ventilation System Operability iVINT DAf t ill L t R NUMDt R .66 htPORT DAf t 17f OTHt M f ACILffit$ INVOLVf D 103 ,
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Ch April 10, 1990, at approximately 1100 CDr, a Control Building /Ataillary Building pressure boundary door uns found by Control Rom operators to be open without a continuous watch having been established. Subsequent evaluatim on April 13, 1990, concluded that the April 10 event as well as a ,
similar event discovered on March 28, 1990, potentially adversely effected Control Rom Bnergency Ventilation System q=vvihility. 'lhis evaluation also concluded that additional events of this nature may have occurred previously during refueling outages.
Subsequent review has detemined that the root cause of these events is inadequate g M ures which resulted in irg vrir control of pressure boundary doors during refueling outages. To prevent recurrence, the Fire Protection inipairment control gdure has been revised to ensure that Control Rom operators are notified prior to establishing a fire inraimant control pemit for any pressure boundary doors.
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TEXT CONTINUATlON !?%"AT! *!".'2 01f a '.1 Tc7"','tJ M "'f R A PAPtaWO Hg 110 6 SD o C Of MANAGEMENT AND DVDGtt,w ASHiNOTON. 0c 20601 f.0141fY hAMk W DDCKkT NUM$t h (2) LtR NUMeth (Gi PA05 (31 E.- "= =.9 WoM Creek Generating Station o [s l0 lo lc l 4[8[2 9l 0 _
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nmunn'um On April 10, 1990, at approximately 1100 CDI', a Control Building
[NA)/ Auxiliary Building [NP) prossure boundary door (NA/NF-DR) was found by Control Rom operators to be open without a omtinuous watch having been established. Subsequent evaluation on April 13, 1990, concluded that this condition potentially adversely effected Control Hom anargency Ventilation Systen (CREYS) [VI) q=mb(14ty. Additionally, on April 13, 1990, it was concluded that a similar event had occurred on March 28, 1990, when a ,
Control Building pressure boundary door (NA-DR) was found open. '1his evaluation also ocncluded that additional events of this nature may have- ;
occurred previously during refueling outages. 1 1
I E E RIPfE M CF M BRIS !
l On March 28, 1990, at approximately 0700 CST, a Control Room operator )
discovered that Door 32201, the door between access control and the ;
comunications corridor, was blocked open in support of work activities '
being perfomed. A fire 4n_ r=4mant control permit had been issued for Door 32201 on March 27, 1990, at approximately 1800 CST which established an hourly fire watch (aawyciate for fire protection considerations) while the door was blocked open. Control Room operators verified that Door 32201 is a i
Control Building pressure boundary door. At the time of this discovery, the plant was in a refueling outags with the core off-lNkwi. CREVS Train 'B' was operating in the recirculation mode while CREVS Train 'A' was inoperable for maintenance.
Following this discovery, Control Rom operators revoked the fire inrmimant control permit at 0718 CST and closed Door 32201 thus restoring the Control Building pressure boundary. Control Rom operators verified that no core alterations had buen parfonned while Door 32201 was open, thus ensuring that operating guidance had been satisfied.
Initial evaluation determined that this event may not have affected CREVS operability since previous tests had shown that the Technical Specification (T/S) Control Room pressurization requirunents could be met with certain Control Building pressure boundary doors blocked open. It was determined that a pressure test would have to be perfonned with Ibor 32201 open to- '
can:1usively prove or disprtne CREVS operability in this configuration.
Disc.ussions were initiated with various personnel to detemine the feasibility of performing this pressure test during the ongoing refueling outage. I_= adiato performance of this pressure test was not feasible. -
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' . Parta Rt UC ON O De o IC of MANAGEMINT AND DVDGE7.VbASHINGTON.DC 7060A I NCILI,y haut ste DOCRt,NuMeth(28 #A06 @
Ltfl NUM0ER ISI via " MOP". :
"E*.9 Wolf Creek Generating Station 0l6l0!0l0l4l8l2 91 0 -
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010 Oi3 Of 0l 6 ms a m. u,u. n o.em u eso< r wrc r n mawm Ori April 10, 1990, at apprendmately 1100 CDr, a Control Room operator discovered that Door 15011, the door between the Atwiliary Building and the
, Control Building Train 'B' Heating, Ventilation, and Air Conditioning System (HVAC) (VI) Equipnent Rom, was blocked open. A fire inraimant control permit had been issued for Door 15011 on April 5, 1990, at approxinately 1545 CDr which established an hourly fire watch (apsvriate for fire ;
protection considerations) while the door was blocked open. Control Rom operators verified that Door 15011 is a Control Building / Auxiliary Building pressure boundary door. At the time of this discovery, the plant was in Mode 6, Refueling, with oore alterations in progress. CREVS Train 'A' was operating in the recirculation mode while CREVS Train 'B' was irgarable.
Following this discovery, control Roam operators determined that Door 15011 ,
had been blocked open in conjunctico with a tanporary nodification. It ;
appeared that with the tanmrary modification installed, in==wiiate restoration of the Control Building /Amiliary Building pressure boundary ;
could not be accanplished as required by the administrative guidance. )
'Iherefore, at approximately 1235 CDP, Control Rom operators susp ded all -
core alterations as required by T/S. Control Room operators then initiated the restoration of the +aamrary modification, including closure of the door prior to resundng core alterations.
Because the Control Building pressure boundary doors are also marked as fire doors and therefore would require a fire inr=4mant control permit prior to blocking it open, Control Rom operators reviewed all outstanding permits to ,
ensure operators were aware of any other pressure boundary docirs tut are
- inpaired. Control Rom operators verified that imediate restoration of the '
pressure boundary in accordance with the administrative guidance could be acconplished should plant conditions regaire such action.
BASIS IM RERRmBIIJ'IY -
'Ihe CPJNS provides the Control Rom with a conditicned atnosphere following various design basis accidents (DBAs) such as loss of coolant accident (IOCA), fuel handling accident, rod ejection, main stmmline break and steam generator tube rupture. 'Ihe CREVS ensures that the ambient air tenperature does not exceed the allowable ta==rature for crntinuous-duty rating for the equipvent and instrumentation cooled by CREVS and the Control Room will reain habitable for Operations perennel during and-follcwing all credible accident conditicos. During the emergency made of oparation, the Control :
Roca is maintained at a positive pressure of greater than or equal to .25 inch water gauge relative to the outside atmosphere to prevent infiltration i
from surrounding areas of unfiltered air. 1 N1C f orm 3esA (649) ,
.. . - . . _ - - . - . . . - - ~ . - - ~ - ... . - - -- . . . .- - . . - . .
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OP MANAGEMENT AND SUDGET.WAEMINGTON.DC 20503
- 1CILITV hAME tu DOCKf t NUMtta L28 Lth NUMSER IS) PAGE (31 vtan M %Q,'b ,N Wolf Creek Generating Station o l6 l0 l0 l0 l4 l 8l 2 9l0 0 l 0l 5 0l0 0l4 or 0 l6 i rsn a wee e ,-,< ,, no,s.awc r= saw nn
'Ihe CREVS consists of two separate and redundant trains which recirculate 1 i the Ccutrol Room air. 'Ihe CREVS Initiates filtered ventilation of the
! Control Rom following receipt of an actuation signal. 'Ihe CREVS design basis is established by the consequences of the limiting DBA which is a IICA 1 in Mode 1, Power Operation, through Mode 4, Hot Shutdown, and a fuel I handling accident in Modes 5 and 6. 'Ihe IICA analysis assumec that only one train of the CREVS is functional due to a sirgle failure which disables the other train. 'Ihe design basis is also established by the potential chlorine gas sources which would have the potential for incapacitating per m unal in l the Control Rom if mitigating actions were not taken. ,
Wolf Creek T/S 3.7.6, which is applicable in all nodes, requires two ,
Jndependent CREVS trains to be operable. For Mode 5, Cold shutdown, and l Node 6, Refueling, with me CREVS train inoperable, T/S 3.7.6 action statement 'a' requires restoring the ineparable CREVS train to rparable r status within 7 days or initiating and maintaining operation of the renaining rpamble CREVS train in the recirculation node. With both CREVS trains ineyarable in Modes 5 and 6, T/S 3.7.6 acticn statement 'b' requires suspending all operations involving core alterations or positive reactivity changes.
Administrative guidance initially provided to Cantrol Rom operators on January 12, 1989, requires that with pressure boundary doors blocked open, a person nust be assigned to the door as a continuous watch utder the direction of the Control Rom and nust be dedicated to closing the door when directed by Control Rom persconel to enable iWiate restoration of the -
boundary. 'Ihe administrative guidance indicates that any work activities requiring a pressure boundary to be branched that cannot meet the continuous watch and innaliate restoration restrictions nust be performed in Mode 5 or i Mode 6 and empliance with aa u.vpriate T/S action statanents nust be i ensured. During each of these events, the. Control Rocm operators were l unaware that these doors had been blocked open and no continuous watch had I been established. 'Iherefore, had plant conditions warranted restoration of the pressure boundaries, the Control Rom operators would not have been aware of the need to take action to restore the pressure bcxuidaries.
Additionally, during the April 10 event, core alterations were in pm,r-s ;
while Door 15011 was blocked open thus violating T/S 3.7.6 action statment
'b'.
l During previous refueling outages, pressurizatica tests of the Control Rom were performed. As a result of these tests, it was determined that in.
order for the CREVS to be capable of performing its design function, the l
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0l0 0l5 OF 0l6 im m . % , w F.,,,,mu .m Control Building pressure boundary had to be maintained thus ensuring the introduction of unfiltered air into the Control Building would remain within the limits assumed in the design basis calculations. The achinistrative guidance provides a list of designated pressure boundary doors as identified
- by these tests to aid the Control Rom operators in maintaining the various boundaries including the Control Building pressure boundary.
As a result of the April 10 evet, on April 13, 1990, discussions were again ;
held concerning the feasibility of performing pressure tests with various doors open. Following these discussions, it was determined that although ,
such pressure tests may prove operability, the testa performed during the previous refueling outages had already established that with either of these ,
doors open the limits assumed in the design basis calculaticms may be exoaartri . Therefore, these events are being reported pursuant to 10 CPR ,
50.73(a)(2)(1)(B) as conditions prohibited by T/S 3.7.6, and 10 CPR 50.73(a)(2)(ii)(B) as conditions outside the design basis.
RXFr CMBE AIO QEEEE' RIVE ACTIGE5
- Subsequent review has detemined that the root cause of these events is L inadequate sucedures which resulted in inever control of pressure boundary doors during refueling outages. During nomal operations, fire '
iwmi mant control permits are prepared by Fire Protection personnel. 'Ihe fire inimimant control pemit is then discussed with control Rom operators prior to establishing the i==4mant. During this discussion, Control Rom '
operators review the pemit against the list of pressure boundary doors ;
contained in the administrative guidance. If the door to be inpaired is a pressure boundary door, the Control Rom operators enter the am.vg.iate T/S action statements, establish the required continuous watch and are aware of the need to contact the continuous watch if restoration of the boundary is required. During refueling outages, although see fire ing=imant control pemits are discussed and reviewed by Control Rom operators, most of the pemits are filed in the Control Rom without discussion or review.
- Additionally, Fire Protection per cuuel were unaware of additicmal considerations for pressure boundary doors ccotained in the administrative guidance and therefore did not identify the need for a continuous watch on the pemits for these doors.
Review of the April 10 event has also identified inocmplete cmmunications during the preparation, review and inpleantation of the tymry ;
NIC Feess 386A (649) .
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TEXT CONTINUATION R ""4"/ #i F.^.",i ni,' # '.".!fle'U ll M ".' O ef" 3 Part Nwo R T N ROJ t'3 . IO IC Of WANAotMENT AND .UDGET,w A.MINGTON.DC 20603 F ACitity NAM 6 (tl DOCK 41 NUM0th (26 4tR WUnt$t h 1.) PA04 (3) vtaa " W3 3*eT Wolf Creek Generating Station o p l0 l0 l0 l 4]8 l 2 9l 0 -
010l 5 - 0l 0 016 0F 0l6 TtXT W more apese e eeuweet, u.e enenenwet NMC 9erm Jann'alIth modification as a contributing factor. During the inplementation of the tanporary modificaticri, Licensed Operations personnel failed to recognize all the requjIanents in the safety evaluation and plan for innediate restoration of the pressure boundary in accordance with the administrative guidance.
To prevent recurrence of these events, Fire Protection personnel have been given a copy of the list of pressure boundary doors contained in the administrative guidance. '1he Fire Protection inraimant ocritrol sveadure has been revised to ensure that control Room operators are notified prior to establishing a fire inraimarit control permit for any of these doors. In addition, information will be provided to Training personnel by July 1, 1990, so that training on the design considerations and basis for the Control Building pressure boundary can be conducted for all Operatier.s piu..cirsel .
l ADDITIGEL IIEGOBH'IGt Because review of the events discussed in this report has shown that fire
-inraimant control permit processing during refueling outages may not have !
included discussicris or reviews with Control Roan operators prior to establishing the inraimant, previous necurrences of this nature may have occurred during previous refueling ouLagos. In one case, during a previous refueling outage, on October 12, 1988, Control Rocan operators discovered Doors 32011 and 32013 (la-IR) open without a continuous watch having been established. Door 32011, the door between the southwest stairwell and access control, and Door 32013, the door between the southwest stairwell and outside, are Control Building pressure boundary doors. As a. result of this discovery, a Control Room pressurization test was conducted on October 22, 1988 with Doors 32011 and 32013 open. Because this test proved that the Control Roam was maintained at a positive pressure greater than or equal to
.25 inch water gauge with Doors 32011 and 32013 open, it was determined that i CREVS were operable. At the time, the potential inpact on the design basis of CREVS was not considered. 'Ihe training on the basis for the Control Building pressure boundary to be conducted as the result of the events discussed in this report will enable Control Rocan operators to recognize potential inpacts of this nature and thus preclude recurrence.
NAC 7eem se6A 16491