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Category:Letter
MONTHYEARML24295A0362024-10-23023 October 2024 Regulatory Audit Plan in Support of Relief Request No. 71; Resubmittal of Relief Request-30 ML24296B2152024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 03: Alternative Request Allowing Removal of the Lower Acceptance Criteria Threshold from Solenoid-Operated Valves ML24296B2142024-10-22022 October 2024 Transmittal of Valve Relief Request (VRR) - 02: Alternative Request Allowing Normally Closed Valves with a Safety Function to Close to Be Exercise Tested Once Per Refueling Cycle IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 ML24296B2172024-10-18018 October 2024 Submittal of Unit 1 Core Operating Limits Report, Revision 34, Unit 2 Core Operating Limits Report, Revision 26, and Unit 3 Core Operating Limits Report, Revision 3 ML24292A2192024-10-18018 October 2024 Core Operating Limits Report Revision 34, 26 and 33 ML24292A0322024-10-17017 October 2024 Th Refueling Outage Steam Generator Tube Inspection Report ML24285A2562024-10-11011 October 2024 License Renewal - Alloy 600 Management Program Plan Response to Request for Additional Information IR 07200044/20244012024-10-0808 October 2024 Independent Spent Fuel Storage Installation Security Inspection Report 07200044/2024401 ML24269A1542024-09-27027 September 2024 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Proposed Life-of-Plant Alternatives for a Pressurizer Thermowell Nozzle Repair at Palo Verde Nuclear Generating Station, Unit 1 ML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) 05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-08-21021 August 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24208A0612024-08-20020 August 2024 Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5 IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator2024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a IR 05000528/20243012024-06-17017 June 2024 NRC Examination Report 05000528/2024301; 05000529/2024301; 05000530/2024301 ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater2024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24129A1482024-05-0707 May 2024 And Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 2024-09-27
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000530/LER-2024-001-01, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-08-21021 August 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation 05000530/LER-2024-002, Invalid Specified System Actuation of Train B Emergency Diesel Generator2024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator 05000530/LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation2024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation 05000529/LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater2024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater 05000528/LER-2017-0012017-06-14014 June 2017 Essential Chiller B Inoperable Due to Refrigerant Leak Resulting in Safety System Functional Failure, LER 17-001-00 for Palo Verde Nuclear Generating Station, Unit 1 Regarding Essential Chiller B Inoperable Due to Refrigerant Leak Resulting in Safety System Functional Failure 05000530/LER-2016-0012017-01-10010 January 2017 Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications, LER 16-001-01 for Palo Verde, Unit 3, Regarding Control Room Essential Filtration System Air Filtration Unit Failure Resulting in a Condition Prohibited by Technical Specifications 05000528/LER-2016-0022016-11-0404 November 2016 Reactor Trip due to Partially Open Pressurizer Main Spray Valve, LER 16-002-00 for Palo Verde, Unit 1, Regarding Reactor Trip due to Partially Open Pressurizer Main Spray Valve 05000528/LER-2016-0012016-06-0909 June 2016 . Leakage from Reactor Coolant Pump 2B Discharge Pipe Instrument Nozzle, LER 16-001-00 for Palo Verde Nuclear Generating Station Unit 1 RE: Leakage from Reactor Coolant Pump 2B Discharge Pipe Instrument Nozzle 05000530/LER-2015-0042016-02-0505 February 2016 Condition Prohibited by Technical Specifications 3.0.4 and 3.7.2 Due to an Inoperable Main Steam Isolation Valve, LER 15-004-01 for Palo Verde, Unit 3, Regarding Condition Prohibited by Technical Specifications 3.0.4 and 3.7.2 Due to an Inoperable Main Steam Isolation Valve ML1034000852010-11-22022 November 2010 LER Palo Verde, Unit 3 - Submittal of Special Report 3-SR-2010-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Inoperable ML0612902562006-04-25025 April 2006 LER 04-02-001 for Palo Verde, Unit 3 Regarding Main Turbine Control System Malfunction Results in Automatic Reactor Trip on Low DNBR ML0602403892005-11-29029 November 2005 Final Precursor Analysis - Palo Verde 1, 2, 3 - Emergency Core Cooling System Piping Voids May Have Prevented Fulfillment of Safety Function ML0530400642005-10-19019 October 2005 Special Report 2-SR-2005-003-00 ML0523802472005-08-13013 August 2005 LER 005-003-00 for Palo Verde, Unit 2 Regarding Two Independent Trains of Auxiliary Feedwater Inoperable ML0413204582004-05-0404 May 2004 Special Report 2-SR-2004-001 for Palo Verde Nuclear Generating Station (PVNGS) Unit 2 Regarding Boron Deposit at Control Element Drive Mechanism Vent ML0303805312003-01-31031 January 2003 LER 03-S01-00 for Palo Verde, Units 1, 2 and 3 Safeguards Material Left Unattended ML0226304872002-09-11011 September 2002 Special Report 1-SR-2002-01 ML0222506692002-08-0707 August 2002 LER 02-S01-00 for Palo Verde Nuclear Station (Pvng), Units 1,2 & 3 Re Reports Discovery of Uncontrolled Safeguards Material in Palo Verde Nuclear Station (PVNGS) Office Complex Outside of Protected Area ML1014705982002-03-0202 March 2002 Event Notification for Palo Verde on Offsite Notification ML0205904412002-02-12012 February 2002 LER 98-003-02, for Palo Verde Units 1, 2 & 3 Re Main Steam Safety Valve As-Found Lift Pressures Outside of Technical Specifications Limits 2024-08-21
[Table view] |
LER-2024-001, Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater |
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text
10 CFR 50.73
Todd A. Horton Senior Vice President Nuclear Regulatory & Oversight
Palo Verde Nuclear Generating Station P.O. Box 52034 Phoenix, AZ 85072 Mail Station 7605 Tel: 623.393.6418 102-08806-TAH/CWD May 23, 2024
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject: Palo Verde Nuclear Generating Station Unit 2 Docket No. STN 50-529 /Renewed License No. NPF-51 Licensee Event Report 2024-001-00
Enclosed, please find the Licensee Event Report (LER) 50-529/2024-001-00 that has been prepared and submitted pursuant to 10 CFR 50.73. This LER reports an event in which Unit 2 had valid specified system actuations of the Unit 2 Train B Emergency Diesel Generator (EDG) and Train B Auxiliary Feedwater (AF).
In accordance with 10 CFR 50.4, copies of this LER are being forwarded to the Nuclear Regulatory Commission (NRC) Regional Office, NRC Region IV, and the Senior Resident Inspector.
No new commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Matthew Cox, Department Leader, Nuclear Regulatory Affairs, at (623) 393-5753.
Sincerely, Horton, Todd Digitally signed by Horton, Todd (Z10098)
(Z10098) Date: 2024.05.23 14:03:14 -07'00' TAH/CWD/cr
Enclosure: Unit 2 Licensee Event Report 2024-001-00 cc: J. Monninger NRC Region IV Regional Administrator W. T. Orders NRC NRR Project Manager for PVNGS L. N. Merker NRC Senior Resident Inspector for PVNGS
A member of the STARS Alliance, LLC
Callaway
Unit 2 Licensee Event Report 2024-001-00
Abstract
At 16:34 Mountain Standard Time (MST) on March 24, 2024, a valid actuation of the B Train Emergency Diesel Generator
(EDG) for the Palo Verde Nuclear Generating Station (PVNGS) Unit 2 occurred due to an undervoltage condition on the
respective 4.16 kilovolt (kV) Class 1E bus. The B Train EDG, the B Train essential spray pond pump, and th e B Train
Auxiliary Feedwater (AF) pump started.
The loss of power to the Class 1E bus and resulting component actuations were the result of the Unit 2 Engineered Safety
Features (ESF) Transformer supply breaker opening. Unit 2 entered Technical Specification (TS) Limiting Condition for
Operation (LCO) 3.8.1, Condition A, for one required offsite circuit inoperable. In addition, the unit also entered TS LCO
3.8.9, Condition A, for the loss of the Class 1E bus, which was exited when the EDG started and restored power to the bus.
TS LCO 3.8.1, Condition A, was exited when the bXVKLQJ was repaired and normal power supply was restored on March 28,
2024.
All times are Mountain Standard Time and approximate unless otherwise indicated.
1. REPORTING REQUIREMENT(S)
This Licensee Event Report (LER) is being submitted pursuant to 10 CFR 50.73 (a)(2)(iv)(A) to report a valid automatic actuation of the circuitry that starts the Emergency Diesel Generator (EDG) (EIIS: EK) for Unit 2 following an undervoltage condition on the affected B Train Class 1E bus on March 24, 2024. The event included actuations of the associated essential spray pond (SP) pumps (EIIS: BS) and the Unit 2 B Train Auxiliary Feedwater (AF) pump (EIIS: BA).
This event was reported to the NRC on March 24, 2024 via the event notification system (EN 57047).
2. INITIAL PLANT CONDITIONS
PVNGS Unit 2 began and remained in MODE 1, 100% power for the duration of the event. There were no structures, systems, or components (SSCs) that were inoperable at the start of the event and contributed to the event.
3. EVENT DESCRIPTION
On March 24, 2024 at 16:34, a valid loss of power (LOP) actuation occurred due to an undervoltage condition on the Unit 2 B Train Class 1E 4.16kV bus. The undervoltage condition resulted from the opening of the B Train ESF Transformer supply breaker. The B Train EDG started and loaded as designed. The EDG start was accompanied by the start of the associated Unit 2 B Train SP pump and the Unit 2 B Train AF pump, as designed for the undervoltage condition. The Unit 2 B Train AF pump was not needed for steam generator level control and no AF valves repositioned. The Unit 2 B Train AF pump did not supply feedwater to the steam generators. Unit 2 entered Technical Specification (TS) Limiting Condition for Operation (LCO) 3.8.1, Condition A for one required offsite circuit inoperable and TS LCO 3.8.9, Condition A for the loss of the Class 1E bus. Unit 2 exited TS LCO 3.8.9 after the EDG started and restored power to the respective Class 1E bus (EIIS: EB).
The NRC was notified by the Emergency Notification System (ENS) report 57047 on March 24, 2024 at 21:48 (00:48 EST) in accordance with 10 CFR 50.72(b)(3)(iv)(A). The NRC residents were notified at the time of the event.
Unit 2 exited TS LCO 3.8.1, Condition A on March 28, 2024 at 01:04 after the bXVKLQJ was repaired and normal alignment restored.
Unit 1 and 3 were unaffected by the event. Unit 2 A Train 4.16kV Class 1E (EIIS: EB) and all Non-Class 1E (EIIS: EA) buses were unaffected by the event.
4. ASSESSMENT OF SAFETY CONSEQUENCES
There were no inoperable structures, systems or components that contributed to this event. The B Train EDG responded as designed to the undervoltage condition on the respective safety bus. The B Train SP and AF pumps actuated as designed for the loss of power.
This event did not result in any challenges to the fission product barriers or result in the release of radioactive materials. This event did not prevent the fulfillment of a safety function as described by 10 CFR 50.73(a)(2)(v), nor did it result in a safety system functional failure.
5. CAUSE OF THE EVENT
The direct cause was a line-to-ground fault on the B phase bushing in the B Train Class 1E 4.16kv switchgear causing an opening of the supply breaker to the ESF transformer, resulting in a loss of power to the B Train Class 1E 4.16kv bus. The apparent cause was water intrusion into the B Train 4.16kV Switchgear cubicle as a result of multiple cracks on the B phase bushings mounting flange.
Walkdowns of the switchgear identified multiple protective relays actuated. Review of Digital Fault Recorder (DFR) data confirmed the line-to-ground fault. Internal inspection of the switchgear revealed water stain residue that tracked from the enclosures ceiling to the bushings electrical taping. External inspection of the switchgear indicated water discoloration and bowing around the roof area of the B phase bushing.
6. CORRECTIVE ACTIONS
The immediate corrective action was to repair the faulted bushing and restore normal power alignment.
A corrective action (CA) is in progress to fix the roof bowing around the faulted bushing. Inspections for all remaining external switchgear bushings on all three units are in progress.
The existing bus connections will be changed from an open-air connection to an enclosed bus connection type as part of scope expansion of an existing ESF Transformer replacement modification. An enclosed bus will help prevent further water intrusion events. This is planned for all three units.
7. PREVIOUS OCCURENCES
On August 14, 2022, a valid actuation of the EDGs for PVNGS Unit 1 B Train and Unit 3 A Train occurred due to an undervoltage condition on their respective 4.16kV Class 1E buses. The loss of power to the Unit 1 and Unit 3 Class 1E buses and resulting component actuations were the result of a startup transformer tripping offline. The cause of the event was attributed to water intrusion into the 13.8kV switchgear cubicle as the result of a heavy rainstorm and high winds, in combination with degraded weatherstripping and conductor insulating boots that are not waterproof. This was reported under LER 1-2022-001-00.
The corrective actions from the previous LER event would not have prevented the event which is the subject of this report.
There have been other events at PVNGS involving water intrusion, but these have not directly caused a similar event as discussed in this report.