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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
ML24177A3222024-06-25025 June 2024
Invalid Specified System Actuation of Train B Emergency Diesel Generator
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
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-2023-003, Control Room Essential Filtration Actuation Signal (CREFAS) Actuation with Essential Spray Pond Pump Start2024-02-0101 February 2024
Control Room Essential Filtration Actuation Signal (CREFAS) Actuation with Essential Spray Pond Pump Start
05000528/LER-2023-001-02, Reactor Trip Following a Main Turbine Trip2024-01-26026 January 2024
Reactor Trip Following a Main Turbine Trip
05000528/LER-2023-002, Reactor Coolant System Degraded Pressure Boundary2023-12-0808 December 2023
Reactor Coolant System Degraded Pressure Boundary
05000529/LER-2023-001-01, Unit 2 Automatic Reactor Trip on Low Steam Generator Water Level Due to Degraded Feedwater Flow2023-11-0909 November 2023
Unit 2 Automatic Reactor Trip on Low Steam Generator Water Level Due to Degraded Feedwater Flow
05000528/LER-2023-001-01, Reactor Trip Following a Main Turbine Trip2023-09-13013 September 2023
Reactor Trip Following a Main Turbine Trip
05000529/LER-2023-001, Regarding Unit 2 Automatic Reactor Trip on Low Steam Generator Water Level Due to Degraded Feedwater Flow2023-08-0101 August 2023
Regarding Unit 2 Automatic Reactor Trip on Low Steam Generator Water Level Due to Degraded Feedwater Flow
05000528/LER-2023-001, Reactor Trip Following a Main Turbine Trip2023-06-0707 June 2023
Reactor Trip Following a Main Turbine Trip
05000528/LER-2022-001, Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses2022-10-11011 October 2022
Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses
05000530/LER-2021-001-01, Reactor Trip During Control Element Assembly Alignment Activities2022-07-14014 July 2022
Reactor Trip During Control Element Assembly Alignment Activities
05000529/LER-2022-001, Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses2022-07-0101 July 2022
Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses
05000528/LER-2021-001-01, Unit 1 and 3 Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses2022-06-0303 June 2022
Unit 1 and 3 Emergency Diesel Generator Actuation on Loss of Offsite Power to Class 4.16 Kv Buses
05000530/LER-2021-001, Reactor Trip During Control Element Assembly Alignment Activities2022-02-0303 February 2022
Reactor Trip During Control Element Assembly Alignment Activities
05000529/LER-2021-002-01, Reactor Trip During Plant Protection System Surveillance Testing2022-01-28028 January 2022
Reactor Trip During Plant Protection System Surveillance Testing
05000529/LER-2021-002, Reactor Trip During Plant Protection System Surveillance Testing2021-07-16016 July 2021
Reactor Trip During Plant Protection System Surveillance Testing
05000529/LER-2021-001, Automatic Actuation of the Reactor Protection System Resulting from a Loss of Reactor Coolant Pumps2021-04-23023 April 2021
Automatic Actuation of the Reactor Protection System Resulting from a Loss of Reactor Coolant Pumps
05000529/LER-2020-001-01, Reactor Trip on Low Steam Generator Level Signal2020-09-10010 September 2020
Reactor Trip on Low Steam Generator Level Signal
05000529/LER-2020-001, Reactor Trip on Low Steam Generator Level Signal2020-04-29029 April 2020
Reactor Trip on Low Steam Generator Level Signal
05000530/LER-2020-001, Condition Prohibited by Technical Specifications Due to Inoperable Spray Pond Pump2020-04-24024 April 2020
Condition Prohibited by Technical Specifications Due to Inoperable Spray Pond Pump
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
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L,ARS; William E. Ide Mail Station 7602 Palo Verde Nuclear Vice President TEL (623) 393-6116 PO Box 52034 Generating Station Nuclear Production FAX (623) 393-6077 Phoenix, AZ 85072-2034 192-0111 0-WEI/DGM/REB September 11, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Unit I Docket No. STN 50-528 License No. NPF-41 Special Report I-SR-2002-01 Attached please find Special Report (SR) 50-528/2002-01-00. This SR reports the inoperability of a portion of the loose parts and vibration monitoring system in Unit 1.
By copy of this letter and the enclosure, this SR is being provided to the NRC Region IV Administrator and the PVNGS Senior Resident Inspector.
No commitments are being made to the NRC by this letter. Please contact Daniel G.
Marks at (623) 393-6492 if you have any questions or require additional information.
Sincerely, Zle'14 WEI/DGM/REB/kg Enclosure cc: E. W. Merschoff (all with enclosure)
J. N. Donohew N. L. Salgado I I--
I
ENCLOSURE Special Report 1-SR-2002-01-00 Technical Requirements Manual limiting condition of operation (TLCO) 3.3.106 requires the loose parts and vibration monitoring system (LPVMS) to be operable in Modes 1 and 2. With one or more channels of the LPVMS inoperable, TLCO Action A.1 requires the channel to be restored to operable within 30 days. Ifthis action cannot be met TLCO Action B.1 requires a special report to be submitted to the NRC within 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to operable status.
On August 14, 2002, with Unit 1 in Mode 1, Power Operations, channel 7 of the LPVMS was declared inoperable due to spurious alarms being generated by noise in the channel.
Cause of the malfunction:
The noise is believed to be caused by a degraded connection at the accelerometer for steam generator #2, which is located in the containment building near steam generator #2 and is not accessible during power operation.
Plans for restoring the channel to Operable status:
The channel will be repaired during the next refueling outage scheduled to begin on September 28, 2002.
