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Category:Letter
MONTHYEARML24312A3152024-11-0505 November 2024 Independent Spent Fuel Storage Installation - Updated Annual Radioactive Effluent Release Report 2023 ML24295A0362024-10-23023 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 IR 05000528/20244022024-10-22022 October 2024 Security Baseline Inspection Report 05000528/2024402 and 05000529/2024402 and 05000530/2024402 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 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 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 IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) 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 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 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 ML24129A1482024-05-0707 May 2024 And Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes 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 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 ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) 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 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 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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LER-2024-001, Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation |
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10 CFR 50.73 A member of the STARS Alliance, LLC Callaway
- Wolf Creek 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 102-08851-TAH/JJM August 21, 2024 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Subject:
Palo Verde Nuclear Generating Station (PVNGS) Unit 3 Docket No. STN 50-530/Renewed License No. NPF-74 Licensee Event Report 2024-001-01 Enclosed, please find the Licensee Event Report (LER) 50-530/2024-001-01 that has been prepared and submitted pursuant to 10 CFR 50.73. This LER supplement provides additional information that was identified through PVNGS evaluation of the Unit 3 loss of power to both channels of the Boron Dilution Alarm Monitoring System with subsequent Technical Specification Violation of 3.3.12 that occurred on April 9, 2024.
The initial LER 2024-001-00 for the Technical Specification violation was provided to the Nuclear Regulatory Commission (NRC) on June 5, 2024. In this LER, the cover letter and enclosure cover page referenced an incorrect unit. Only Unit 3 was affected. This issue has been documented in the corrective action program.
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 S. Cox, Department Leader, Nuclear Regulatory Affairs, at (623) 393-5753.
Sincerely, TAH/JJM/cr Enclosure: Unit 3 Licensee Event Report 2024-001-01 cc:
J. Monninger NRC Region IV Regional Administrator W. T. Orders NRC NRR Project Manager for PVNGS N. Cuevas NRC Acting Senior Resident Inspector for PVNGS Horton, Todd (Z10098)
Digitally signed by Horton, Todd (Z10098)
Date: 2024.08.21 12:45:31
- - 07'00'
ENCLOSURE Unit 3 Licensee Event Report 2024-001-01
Abstract
On 4/9/2024 at 1100, while in a refueling outage at zero percent power, Unit 3 control room experienced an unplanned partial loss of power to annunciator windows in the Control Room due to a planned down power of an electrical power supply for the performance of maintenance. The control room entered Technical Specification (TS) Limited Condition for Operation (LCO) 3.3.12 Boron Dilution Alarm System (BDAS) Condition A and B. Personnel from the Chemistry Department obtained samples until power was restored and the BDAS returned to OPERABLE 4/9/2024 at 1233 when the TS LCO was exited.
On 4/13/2024 at approximately 0630, it was discovered that the sample was obtained from an incorrect sample location. Further TS LCO 3.3.12 Condition B was not met as redundant samples were not taken. The NRC resident inspectors were notified of this event.
No similar event has occurred at PVNGS in the last three years.Page of
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050 On 4/13/2024, the Chemistry Supervisor was reviewing the samples and realized that the samples were obtained from a different sample point than specified in plant procedures for the conditions of the RCS system being in Shutdown Cooling (SDC) at the time of the event. Furthermore, the Chemistry Supervisor noticed the samples were not obtained redundantly to validate boron concentration as required by TS LCO 3.3.12 Condition B. The supervisor contacted the control room of the findings.
Units 1 and 2 were unaffected by the event and both remained in MODE 1 at 100% power.
5. ASSESSMENT OF SAFETY CONSEQUENCES
Operability of the BDAS channels are necessary to meet the assumptions of the safety analyses to mitigate the consequences of an inadvertent boron dilution event as described in the UFSAR Chapter 15, Revision 22. Unit 3 was in MODE 5 on 4/9/2024 when both channels of the BDAS became inoperable. During the time of the event, there were no MODE changes and no inadvertent boron dilutions.
6. CAUSE OF THE EVENT
The direct cause of the event was lack of formality and adequate details in the verbal communications between the Operations and Chemistry departments. The Operations Department and Chemistry Department communications for the LCO required boron samples did not specify all requirements. The apparent cause is that the Chemistry Department procedure did not contain specific sampling requirements necessary to satisfy the required actions of LCO 3.3.12 Condition B.
7. CORRECTIVE ACTIONS
Immediate actions included the restoration of power supplies to the annunciator panels which subsequently restored BDAS to OPERABLE status.
Actions included briefing Operations Staff and Chemistry Staff including expected behaviors regarding control room communication to outside groups and the importance of thoroughly communicating LCO details. Additional actions include procedure revisions for the Chemistry Department to add guidance on sampling locations and other critical task information related to the LCO requirements. The Operations Department will revise the Loss of Annunciators procedure to add steps directing Chemistry to use the guidance.
8. PREVIOUS SIMILAR EVENTS
No similar events have occurred in the prior three years.
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Palo Verde Nuclear Generating Station (PVNGS) Unit 3 00530 2024 001 01