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Category:Letter
MONTHYEARIR 05000482/20243012025-01-30030 January 2025 Notification of NRC Initial Operator Licensing Examination 05000482/2024301 ML25023A0442025-01-24024 January 2025 Acknowledgement of Response to U.S. Nuclear Regulatory Commission Inspection Report 05000482/2024003 and Disputed Non Cited Violation IR 05000482/20254012025-01-22022 January 2025 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000482/2025401 ML25010A3692025-01-14014 January 2025 Regulatory Audit in Support of Review of License Amendment and Exemption Requests for Risk-Informed Resolution to GSI-191 ML25006A0942025-01-0606 January 2025 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24366A1612024-12-31031 December 2024 Operating Corporations (Wcnocs) Contest Response to Non-Cited Violation 2024003-01 - NRC Inspection Report 05000482/2024003 IR 05000482/20240142024-12-17017 December 2024 Comprehensive Engineering Team Inspection Report 05000482/2024014 ML24352A4382024-12-17017 December 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b Commissioners ML24352A0322024-12-17017 December 2024 Notification of Post Approval Site Inspection for License Renewal and Request for Information ML24347A0122024-12-12012 December 2024 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) 05000482/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 IR 05000482/20244022024-12-0505 December 2024 Security Baseline Inspection Report 05000482/2024402 ML24337A1232024-12-0202 December 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 239 ML24337A0132024-12-0202 December 2024 Cycle 27 Core Operating Limits Report, Revision 1 ML24332A1262024-11-27027 November 2024 Notice of Intent to Contest Non-Cited Violation (NCV) 05000482/2024003-01, and Request for Additional Time to Provide Wolf Creek Nuclear Operating Corporation’S (WCNOC) NCV Response ML24306A2192024-11-0101 November 2024 Results of the Steam Generator Tube Inservice Inspection During the 26th Refueling Outage to Reflect TSTF-577 Reporting Requirements ML24295A3792024-11-0101 November 2024 Integrated Inspection Report 05000482/2024003 IR 05000482/20240032024-11-0101 November 2024 Integrated Inspection Report 05000482/2024003 IR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 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 ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 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 IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report 2025-01-06
[Table view] 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
[Table view] |
LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
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4822024002R00 - NRC Website |
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text
P.O. Box 411 l Burlington, KS 66839 l 620-364-8831 Robert J. Bayer Plant Manager October 21, 2024 000655 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482: Licensee Event Report 2024-002-00, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve Commissioners and Staff:
The enclosed Licensee Event Report (LER) 2024-002-00 is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(A) for the completion of plant shutdown required by Technical Specifications.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4015, or Dustin Hamman at (620) 364-4204.
Sincerely, Robert J. Bayer RJB/jkt
Enclosure:
LER 2024-002-00 cc:
M. R. Bloodgood (NRC), w/e S. S. Lee (NRC), w/e J. D. Monninger (NRC), w/e Senior Resident Inspector (NRC), w/e WC Licensing Correspondence WO 24-000655, w/e
Abstract
Wolf Creek Generating Station
00482 3
Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve 08 23 2024 2024 002 00 10 21 2024 1
98
Jason Knust, Lead Licensing Engineer 620-364-8831 B
BA FCV YES
01 31 2025 All times are Central Daylight Time (CDT).
At 0500 on 8/20/24, Wolf Creek entered Condition C of Technical Specification (TS) 3.7.5 when the turbine driven auxiliary feedwater (TDAFW) pump train was declared inoperable for planned maintenance. Emergent work was declared at 0200 on 8/21/24 due to erratic response of ALHV0010, TDAFW pump discharge valve to the 'B' steam generator. At 0316 on 8/22/24 while performing troubleshooting on the valve, the TDAFW pump tripped on overspeed. The erratic behavior of the valve could not be repeated and was considered an anomalous event. It was determined that work to restore the TDAFW pump could not be completed within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time of Required Action C.1 of TS 3.7.5. A Notice of Enforcement Discretion (NOED) was verbally requested and was subsequently granted by the Nuclear Regulatory Commission (NRC) at 0100 on 8/23/24. While the TDAFW pump was being restored, ALHV0010 began acting erratically again and could not be controlled. This invalidated the NOED, so a plant shutdown was initiated at 0800 on 8/23/2024. Mode 3 was reached at 1024, and Mode 4 was reached at 1651 on the same day. Therefore, this event is reportable per 10 CFR 50.73(a)(2)(i)(A) as a plant shutdown required by TS. Page of
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050 BASIS FOR REPORTABILITY TS Limiting Condition of Operation (LCO) 3.7.5 requires three AFW trains be operable while the unit is in Modes 1, 2, and
- 3. Condition C is entered when one AFW train becomes inoperable for reasons other than Condition A (one steam supply to the TDAFW pump inoperable) or Condition B (one Essential Service Water (ESW) supply to the TDAFW pump inoperable). Required Action C.1 is to restore the AFW train to operable status with a Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If this Completion Time is not met, Condition D is entered. Required Action D.1 is to be in Mode 3 with a Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Required Action D.2 is to be in Mode 4 with a Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The initiation of any nuclear plant shutdown required by TS is reportable within four hours of the event in accordance with 10 CFR 50.72(b)(2)(i). On 8/23/2024 at 0800, plant shutdown was initiated and in accordance with 10 CFR 50.72(b)(2)(i),
ENS notification 57284 was made by Wolf Creek at 0802. Plant shutdown was completed when Mode 4 was reached at 1651 on the same day. Therefore, this event is being reported as a 60-day licensee event report (LER) for the completion of a nuclear plant shutdown required by TS in accordance with 10 CFR 50.73(a)(2)(i)(A).
CAUSE
The cause investigation is still ongoing for the failure of ALHV0010. The cause will be documented in the supplement to this LER.
CORRECTIVE ACTIONS
Initial corrective actions included restoring ALHV0010 to operable status on 8/25/24. Additional corrective actions will be documented in the supplement to this LER.
SAFETY SIGNIFICANCE
The safety significance of this event was low. The reactor was shutdown in accordance with site procedures and all safety systems operated as designed. In addition, both motor driven AFW pump trains were verified to be operable during the time the TDAFW pump train was inoperable.
OPERATING EXPERIENCE/PREVIOUS EVENTS There have been no occurrences of Wolf Creek Generating Station having to shut down as required by TS in the past three years. Nor have their been any LERs submitted from Wolf Creek in the last three years related to AFW system malfunctions. LER 2024-001-00 was submitted by Wolf Creek on 7/2/24 which was related to AFW discharge valves.
However, this event occurred only due to entry into a Mode not allowed by TS due to post-maintenance testing not being performed. The testing was done subsequent to discovery and all valves were able to perform their intended functions.
3 3
Wolf Creek Generating Station 00482 2024 002 00