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Category:Letter
MONTHYEARML24306A2192024-11-0101 November 2024 Results of the Steam Generator Tube Inservice Inspection During the 26th Refueling Outage to Reflect TSTF-577 Reporting Requirements IR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 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 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 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 ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third 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 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) 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 ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000482/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-2017-0032017-11-0202 November 2017 ARV and MSSV Tornado Missile Vulnerabilities Result in Unanalyzed Condition, LER 17-003-00 for Wolf Creek Generating Station Regarding ARV and MSSV Tornado Missile Vulnerabilities Result in Unanalyzed Condition 05000482/LER-2017-0012017-05-17017 May 2017 Condition Prohibited by Technical Specifications Due to One Train of Component Cooling Water Inoperable, LER 17-001-00 for Wolf Creek Regarding Condition Prohibited by Technical Specifications Due to One Train of Component Cooling Water Inoperable 05000482/LER-2016-0022017-01-16016 January 2017 Loss of Switchyard Bus Results in Emergency Diesel Generator Actuation, LER 16-002-00 for Wolf Creek Generating Station Regarding Loss of Switchyard Bus Results in Emergency Diesel Generator Actuation 2024-07-02
[Table view] |
LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve |
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Report date: |
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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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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.
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Wolf Creek Generating Station 00482 2024 002 00