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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
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LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing |
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10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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4822024001R01 - NRC Website |
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P.O. Box 411 l Burlington, KS 66839 l 620-364-8831 Robert J. Bayer Plant Manager October 22, 2024 000664 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Reference:
Letter 000523, dated July 2, 2024, from R. J. Bayer, WCNOC, to USNRC Subject:
Docket No. 50-482: Licensee Event Report 2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable due to Missed Post-Maintenance Testing Commissioners and Staff:
The Reference submitted Licensee Event Report (LER) 2024-001-00, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable due to Missed Post-Maintenance Testing. The enclosed supplement revises the cause and corrective actions. LER 2024-001-01 is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) regarding an operation or condition prohibited by Wolf Creek Generating Stations 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 2024-001-01 (
Abstract
Wolf Creek Generating Station
00482 3
Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable due to Missed Post-Maintenance Testing 05 09 2024 2024 001 01 10 22 2024 3
00
Jason Knust, Lead Licensing Engineer 620-364-8831
At 2330 Central Daylight Time (CDT) on 5/9/2024, during mode ascension coming out of Refueling Outage 26 (RF26), it was discovered that no post-maintenance testing had been performed on three air operated discharge valves which had maintenance performed on them during RF26. These valves provide flow from the turbine driven auxiliary feedwater pump to the steam generators. This discovery was made after the unit had gone from Mode 4 to Mode 3. With no post-maintenance testing performed on these three valves, they would have to be declared out of service which would cause the turbine driven AFW pump train to be inoperable in Mode 3. Because one required train of AFW was inoperable, LCO 3.7.5 was not met when the unit entered into Mode 3. Immediately following discovery, WCGS personnel began the process of testing the three valves. By 0215 CDT on 5/10/2024, testing was finished with all three valves having passed satisfactorily. The valves were returned to service at this time and the turbine driven AFW pump train was declared operable. TS LCO 3.0.4 only allows entry into a Mode of applicability for an unmet LCO when certain requirements are met. However, none of these requirements were met. Therefore, upon entry into Mode 3, WCGS violated TS LCO 3.0.4. This event is therefore reportable per 10 CFR 50.73(a)(2)(i)(B) as an operation or condition prohibited by TS. Page of
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050 EVENT DESCRIPTION (cont.)
c. When an allowance is stated in the individual value, parameter, or other Specification.
Required Action C.1 of LCO 3.7.5 has a 72-hour Completion Time, so continued operation in this Condition is time limited; no specific risk assessment was performed for entry into Mode 3 with the turbine driven AFW pump train inoperable; and there are no allowances in LCO 3.7.5 (or any other Specification) for entry into Mode 3 with the turbine driven AFW pump train inoperable. Therefore, none of the requirements of LCO 3.0.4 were met when WCGS entered Mode 3 with LCO 3.7.5 not met.
BASIS FOR REPORTABILITY From the time the unit entered Mode 3 until the testing was completed and the valves restored to service, the unit would have been in Condition C for approximately 42 1/2 hours. This is less than the 72-hour Completion Time to restore the turbine driven AFW pump train to operable status. As such, LCO 3.7.5 was not violated. However, the unit did enter Mode 3 while not meeting LCO 3.7.5. None of the requirements stated in LCO 3.0.4 were met during this time so WCGS was in violation of LCO 3.0.4. Therefore, this event is reportable per 10 CFR 50.73(a)(2)(i)(B) as an operation or condition prohibited by TS.
CAUSE In the NRC 2nd Quarter Integrated Inspection report for WCGS, a semi-annual trend was identified based on a number of examples of improperly planning or performing PMTs. A causal evaluation was done that incorporated these examples including the issue that is discussed in this report. The probable cause was determined to be a decrease in the proficiency and experience levels of personnel to promote adequate implementation of the PMT program.
CORRECTIVE ACTIONS Immediate corrective actions included performing the missed post-maintenance testing, and once completed satisfactorily, declaring the turbine driven AFW pump train operable. Corrective actions that have been taken or are in progress include SROs participating in discussions, as well as teaching and learning sessions with Operations leadership and Shift Managers regarding developing PMT plans and acceptable tracking methods. Corrective actions planned include developing and presenting a PMT seminar with planners to discuss the PMT procedure, operating experience, and a learning activity to plan a PMT.
SAFETY SIGNIFICANCE The safety significance of this event was low. All three valves successfully passed their post-maintenance testing the first time. Therefore, had there been an event that would have required the AFW system to operate during the time the unit was in Mode 3 prior to testing the valves, all three trains of the system would have been capable of performing their intended functions. In addition, both motor driven AFW pump trains were verified to be operable prior to entering Mode 3.
OPERATING EXPERIENCE/PREVIOUS EVENTS A search of the corrective action program revealed that there have been no occurrences of making a Mode change not allowed by LCO 3.0.4 at WCGS in the past three years.
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Wolf Creek Generating Station 00482 2024 001 01