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Category:Licensee Event Report (LER)
MONTHYEAR05000482/LER-2024-002-01, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-12-11011 December 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2022-001, Low Steam Generator Level Due to Main Feedwater Valve Failure Caused Reactor Trip2022-09-14014 September 2022 Low Steam Generator Level Due to Main Feedwater Valve Failure Caused Reactor Trip 05000482/LER-2021-004, Low Steam Generator Level Due to Main Feedwater Valve Failure Caused Automatic Reactor Trip2021-10-18018 October 2021 Low Steam Generator Level Due to Main Feedwater Valve Failure Caused Automatic Reactor Trip 05000482/LER-2021-003, Re Automatic Reactor Trip Due to Low Steam Generator Level2021-07-12012 July 2021 Re Automatic Reactor Trip Due to Low Steam Generator Level 05000482/LER-2021-001-01, Re Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications2021-03-17017 March 2021 Re Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications 05000482/LER-2021-001, Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications2021-02-15015 February 2021 Entry Into Mode 4 with Excessive Containment Valve Leakage Resulted in a Condition Prohibited by Technical Specifications 05000482/LER-2020-001-01, Plant Shutdown Due to Inoperable Containment Purge Isolation Valves2020-07-0606 July 2020 Plant Shutdown Due to Inoperable Containment Purge Isolation Valves 05000482/LER-2019-002, Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure2019-10-14014 October 2019 Emergency Diesel Generator Inoperable Due to Temperature Control Valve Failure 05000482/LER-2019-001, Re Valid Actuation of One of the Emergency Diesel Generators2019-07-18018 July 2019 Re Valid Actuation of One of the Emergency Diesel Generators 05000482/LER-2018-002, Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications2019-02-27027 February 2019 Modification Activities Affected Control Room Envelope Boundary Causing a Condition Prohibited by Technical Specifications 05000482/LER-2018-001, Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications2018-10-0404 October 2018 Inappropriate Use of Blind Flange for Containment Isolation Valve Results in Condition Prohibited by Technical Specifications 05000482/LER-1917-003, Regarding ARV and MSSV Tornado Missile Vulnerabilities Result in Unanalyzed Condition2017-11-0202 November 2017 Regarding ARV and MSSV Tornado Missile Vulnerabilities Result in Unanalyzed Condition 05000482/LER-1917-001, Regarding Condition Prohibited by Technical Specifications Due to One Train of Component Cooling Water Inoperable2017-05-17017 May 2017 Regarding Condition Prohibited by Technical Specifications Due to One Train of Component Cooling Water Inoperable 05000482/LER-2016-002, Regarding Loss of Switchyard Bus Results in Emergency Diesel Generator Actuation2017-01-16016 January 2017 Regarding Loss of Switchyard Bus Results in Emergency Diesel Generator Actuation 05000482/LER-2016-001, Regarding Power Potential Transformer Overloading Results in Emergency Diesel Generator Inoperability2016-03-28028 March 2016 Regarding Power Potential Transformer Overloading Results in Emergency Diesel Generator Inoperability 05000482/LER-2015-004, Regarding Inadequate Procedure Error Results in Two Containment Isolation Valves Being in a Condition Prohibited by Technical Specifications2015-07-0101 July 2015 Regarding Inadequate Procedure Error Results in Two Containment Isolation Valves Being in a Condition Prohibited by Technical Specifications 05000482/LER-2015-003, Regarding Manual Reactor Trip Due to High Steam Generator Level Transient at Low Power2015-07-0101 July 2015 Regarding Manual Reactor Trip Due to High Steam Generator Level Transient at Low Power 05000482/LER-2015-002, Regarding Two Control Room Air Conditioning Trains Inoperable Due to Failure to Meet Surveillance Requirement2015-06-15015 June 2015 Regarding Two Control Room Air Conditioning Trains Inoperable Due to Failure to Meet Surveillance Requirement 05000482/LER-2015-001, Regarding Personnel Error Causes Two Inoperable Residual Heat Removal Trains2015-03-25025 March 2015 Regarding Personnel Error Causes Two Inoperable Residual Heat Removal Trains 05000482/LER-2014-004, Regarding Condition Prohibited by Technical Specifications Due to an Instrument Tunnel Sump Level Indication Transmitter Incompatible with the Containment Environment2014-07-31031 July 2014 Regarding Condition Prohibited by Technical Specifications Due to an Instrument Tunnel Sump Level Indication Transmitter Incompatible with the Containment Environment 05000482/LER-2014-003, Regarding Failure of Safety Injection Accumulator Vent Line Due to Low Stress - High Cycle Fatigue Results in Degraded Reactor Coolant Boundary2014-06-19019 June 2014 Regarding Failure of Safety Injection Accumulator Vent Line Due to Low Stress - High Cycle Fatigue Results in Degraded Reactor Coolant Boundary 05000482/LER-2014-001, Regarding Failure to Comply with Required Action of Technical Specification 3.4.3 While Performing a Vacuum Fill of the Reactor Coolant System2014-03-0606 March 2014 Regarding Failure to Comply with Required Action of Technical Specification 3.4.3 While Performing a Vacuum Fill of the Reactor Coolant System 05000482/LER-2013-010, Technical Specification Required Shutdown Due to a Nonfunctional Class 1E Electrical Equipment Air Conditioning Unit Caused by Foreign Material2013-12-17017 December 2013 Technical Specification Required Shutdown Due to a Nonfunctional Class 1E Electrical Equipment Air Conditioning Unit Caused by Foreign Material 05000482/LER-2013-009, Operating Corp, Post-Fire Safe Shutdown Design Issue May Impact Ability to Achieve Safe Shutdown2013-12-0505 December 2013 Operating Corp, Post-Fire Safe Shutdown Design Issue May Impact Ability to Achieve Safe Shutdown 05000482/LER-2013-008, Regarding Technical Specification Required Shutdown Due to a Nonfunctional Class 1E Electrical Equipment Air Conditioning Unit2013-11-12012 November 2013 Regarding Technical Specification Required Shutdown Due to a Nonfunctional Class 1E Electrical Equipment Air Conditioning Unit 05000482/LER-2013-007, Nonfunctional Class 1E Electrical Equipment Air Conditioning Unit Results in Longer than Technical Specification Completion Time2013-08-14014 August 2013 Nonfunctional Class 1E Electrical Equipment Air Conditioning Unit Results in Longer than Technical Specification Completion Time 05000482/LER-2013-006, Regarding Technical Specification Required Shutdown Due to a Nonfunctional Class 1 E Electrical Equipment Air Conditioning Unit2013-07-0808 July 2013 Regarding Technical Specification Required Shutdown Due to a Nonfunctional Class 1 E Electrical Equipment Air Conditioning Unit 05000482/LER-2013-005, Regarding Fatigue Failure of Jacket Water Pressure Switch Diaphragm Results in Loss of the B Diesel Generator2013-05-13013 May 2013 Regarding Fatigue Failure of Jacket Water Pressure Switch Diaphragm Results in Loss of the B Diesel Generator 05000482/LER-2013-004, Regarding Torque Requirement Human Performance Issue Caused Nonfunctional Class 1 E Electrical Equipment Air Conditioning Unit and an Inoperable Control Room Air Conditioning Unit2013-05-0303 May 2013 Regarding Torque Requirement Human Performance Issue Caused Nonfunctional Class 1 E Electrical Equipment Air Conditioning Unit and an Inoperable Control Room Air Conditioning Unit 05000482/LER-2013-003, Regarding Movement of Irradiated Fuel Progressed After Non-Conservative Decision Making Resulted in Removal of One Source Range Monitor from Service2013-04-15015 April 2013 Regarding Movement of Irradiated Fuel Progressed After Non-Conservative Decision Making Resulted in Removal of One Source Range Monitor from Service 05000482/LER-2013-002, Regarding Pressure Boundary Leakage on a Seal Water Injection Drain Line Due to Low Stress High Cycle Fatigue2013-04-0202 April 2013 Regarding Pressure Boundary Leakage on a Seal Water Injection Drain Line Due to Low Stress High Cycle Fatigue 05000482/LER-2013-001, Regarding Broken Cylinder Head Stud Causes Inoperable Diesel Generator Longer than Technical Specification Completion Time2013-03-11011 March 2013 Regarding Broken Cylinder Head Stud Causes Inoperable Diesel Generator Longer than Technical Specification Completion Time 05000482/LER-2012-005, Regarding Calculation Assumptions Lead to Inadequate Procedure, Resulting in LCO 3.0.3 Entry Due to Non- Functional Class 1 E Electrical Equipment Air Conditioning Unit2012-07-23023 July 2012 Regarding Calculation Assumptions Lead to Inadequate Procedure, Resulting in LCO 3.0.3 Entry Due to Non- Functional Class 1 E Electrical Equipment Air Conditioning Unit 05000482/LER-2012-004, Regarding Two Charging Pumps Capable of Injecting Into the RCS Due to Inadequate Definition of Centrifugal Charging Pump in LCO 3.4.122012-07-0303 July 2012 Regarding Two Charging Pumps Capable of Injecting Into the RCS Due to Inadequate Definition of Centrifugal Charging Pump in LCO 3.4.12 05000482/LER-2012-003, Regarding B Train ECCS and Containment Spray System Inoperable Due to Damaged Watertight Containment Spray Pump Door Seal2012-06-18018 June 2012 Regarding B Train ECCS and Containment Spray System Inoperable Due to Damaged Watertight Containment Spray Pump Door Seal 05000482/LER-2012-002, Regarding One Train of Automatic Safety Injection Blocked During Entry Into Mode 3 Due to Procedural Weakness2012-05-17017 May 2012 Regarding One Train of Automatic Safety Injection Blocked During Entry Into Mode 3 Due to Procedural Weakness 05000482/LER-2012-001, For Wolf Creek Regarding Failure of 345 Kv Switchyard Breaker Due to Internal Fault Resulting in Reactor Trip and Coincident Loss of Offsite Power2012-03-12012 March 2012 For Wolf Creek Regarding Failure of 345 Kv Switchyard Breaker Due to Internal Fault Resulting in Reactor Trip and Coincident Loss of Offsite Power 05000482/LER-2011-009-01, Regarding Inadequate Oil Analysis Causes Inoperable Auxiliary Feedwater Pump Longer than Allowed Outage Time2012-01-20020 January 2012 Regarding Inadequate Oil Analysis Causes Inoperable Auxiliary Feedwater Pump Longer than Allowed Outage Time 05000482/LER-2011-011, Regarding Inadequate Analysis Assumptions Resulting in Deficient Control Room Evaluation Procedure2012-01-0303 January 2012 Regarding Inadequate Analysis Assumptions Resulting in Deficient Control Room Evaluation Procedure 05000482/LER-2011-004-02, Regarding Automatic Safety Injection Actuation Due to Operating Crew Failure to Follow Procedures2011-12-28028 December 2011 Regarding Automatic Safety Injection Actuation Due to Operating Crew Failure to Follow Procedures 05000482/LER-2011-009, Regarding Inadequate Oil Analysis Caused Inoperable Auxiliary Feedwater Pump Longer than Required Action Completion Time2011-10-0707 October 2011 Regarding Inadequate Oil Analysis Caused Inoperable Auxiliary Feedwater Pump Longer than Required Action Completion Time 05000482/LER-2011-004-01, Regarding Automatic Safety Injection Actuation Due to Operation Crew Failure to Follow Procedures2011-09-29029 September 2011 Regarding Automatic Safety Injection Actuation Due to Operation Crew Failure to Follow Procedures 05000482/LER-2011-008, Regarding Post-Fire Safe Shutdown Latent Design Issue May Cause Essential Service Water System Flow Imbalance2011-09-19019 September 2011 Regarding Post-Fire Safe Shutdown Latent Design Issue May Cause Essential Service Water System Flow Imbalance 05000482/LER-2011-007, Manual Reactor Trip Due to Failed Controller Cards in the B Feedwater Pump Turbine Control System2011-08-24024 August 2011 Manual Reactor Trip Due to Failed Controller Cards in the B Feedwater Pump Turbine Control System 05000482/LER-2011-006, For Wolf Creek Generating Station, Regarding Auxiliary Feedwater Actuation Due to Operators Inability to Control Steam Generator Level in Mode 42011-07-25025 July 2011 For Wolf Creek Generating Station, Regarding Auxiliary Feedwater Actuation Due to Operators Inability to Control Steam Generator Level in Mode 4 05000482/LER-2011-005, Regarding Procedure Weakness Allowed Entry Into Mode 6 with One Source Range Monitor Inoperable2011-06-29029 June 2011 Regarding Procedure Weakness Allowed Entry Into Mode 6 with One Source Range Monitor Inoperable 05000482/LER-2011-003, Cancellation of LER 11-003-00 for Wolf Creek Re Diesel Generator Declared Inoperable Due to Inadequate Reinstallation of Pipe Connection Resulting in Excessive Governor Oil Coolant Leak2011-06-0909 June 2011 Cancellation of LER 11-003-00 for Wolf Creek Re Diesel Generator Declared Inoperable Due to Inadequate Reinstallation of Pipe Connection Resulting in Excessive Governor Oil Coolant Leak 2024-07-02
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LER-2002-005, From Wolf Creek Generating Station Regarding Engineered Safety Features Actuation Including Emergency Diesel Generator Start |
Event date: |
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Reporting criterion: |
10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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4822002005R00 - NRC Website |
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text
a W>LF CREEK-
'NUCLEAR OPERATING CORPORATION Gary B. Fader Vice President Technical Services OCT 2-4 2002 ET 02-0047 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482: Licensee Event Report 2002-005-00, Engineered
- - Safety Features Actuation including Emergency Diesel Generator Start.
Gentlemen:
The enclosed Licensee Event Report (LER) 2002-005-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(iv)(A) regarding an Engineered Safety Feature Actuation at-Wolf Creek -
Generating Station.-
Wolf Creek Nuclear Operating Corporation has made no commitments in the enclosed LER.
If you should have any questions-regarding this submittal, please contact me at (620) 364-4034 or Mr. Tony Harris at (620) 364-4038.
Very truly yours,
- - Gary B. Fader GBF/rIg Enclosure cc:
J. N. Donohew (NRC), w/e D. N. Graves (NRC), w/e E. W. Merschoff (NRC), wle Senior Resident Inspector (NRC), w/e -
~ PO Box 411 /Burlington, KS 66839/ Phone (620) 364-8831 An Equal Opportunity Employer M/F/HCNVET
Abstract
On September 9, 2002, at 3:58 p.m. Central Daylight Time (CDT), Wolf Creek Generating Station (WCGS) experienced a Degraded Voltage signal on Emergency Power Bus NB01 causing an automatic actuation of the
'A" Emergency Diesel Generator ('A" EDG) and the associated Load Shedder and Emergency Load Sequencer (LSELS). The cause of the degraded voltage signal was determined to be due to a hardware failure in an electronic relay driver card in the LSELS degraded voltage circuitry. An actual degraded emergency bus voltage situation did not exist.
The safety significance of this event is low. All safety related equipment responded to the actuation signal as expected. There were no adverse effects on the health and safety of the public.
(if more space is required, use additional copies of (If more space is required, use additional copies of NRC Form 366A)
Root Cause:
The failure that initiated the degraded voltage alarm and subsequent opening of the normal feeder breaker to bus NB01 has been identified as occurring in an integrated circuit (IC) on a relay driver board in the NF039A cabinet. Specifically, a logic gate between pins 4, 6 and 7 in the "U1" IC on relay driver board #17 in the NF039A cabinet experienced a hardware failure to a logic Hi condition. This caused LSELS output relays 1148 and 1149 to energize and trip the NB01 feeder breakers.
Corrective Actions
Troubleshooting activities performed following this event concluded that the failure of the "Ul" chip on the relay driver board described in the root cause was the initiator of this event, and was classified as a random failure of an electronic semi-conductor integrated circuit. Following successful testing of a replacement board, it was installed and the system restored to service. LSELS was declared operable at 11:53 p.m. on September 9, 2002.
Safety Significance
The safety significance of this event is low. This event is bounded by the current licensing basis analysis as reported in Wolf Creek Generating Station (WCGS) Updated Safety Analysis Report (USAR), section 8.3.1,
'AC Power Systems", as indicated in Table 8.3.4. All safety related equipment performed as designed and there were no adverse effects on the health and safety of the public.
Previous Events:
Research into the corrective action program database was conducted for keywords "LSELS" and "sequencer", as well as systems NF and SA. No similar failures were found, nor were any other ESF actuations found attributed to these electronic cards. There are sixty (60) cards of this type used at WCGS.
They are all used in the NF and SA systems. Twenty-eight (28) are used in the NF cabinets, and thirty-two (32) are used in the SA cabinets. There have been six (6) failures in seventeen (17) years. The reliability of these boards, over a one-year period, is 99.4%. Three of these failures have occurred in NF039A, two in SA075B and one in the SA075A cabinet. One failure occurred in 1988, one in 1992, one in 1993, one in 2001 and two in 2002. To date, this event has been the only significant incident resulting from a failure of these electronic cards. The other failures have been minor equipment failures and were corrected under the work controls process.
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05000482/LER-2002-001, Re Voluntary Report of Emergency Diesel Generator Heat Exchanger Tube Degradation | Re Voluntary Report of Emergency Diesel Generator Heat Exchanger Tube Degradation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) | 05000482/LER-2002-002 | Mode Change with RCS Unidentified Leakage Greater than Technical Specification 3.4.13 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000482/LER-2002-003 | 1 OF 4 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000482/LER-2002-004, Cable Interaction That Could Potentially Affect Refueling Water Storage Tank Inventory | Cable Interaction That Could Potentially Affect Refueling Water Storage Tank Inventory | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000482/LER-2002-005, From Wolf Creek Generating Station Regarding Engineered Safety Features Actuation Including Emergency Diesel Generator Start | From Wolf Creek Generating Station Regarding Engineered Safety Features Actuation Including Emergency Diesel Generator Start | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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