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Category:Letter
MONTHYEARIR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation 05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 The Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee 05000412/LER-2023-003-01, Missile Barrier Door Left Open Resulting in a Loss of Safety Function2024-02-20020 February 2024 Missile Barrier Door Left Open Resulting in a Loss of Safety Function IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection 2024-09-17
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation 05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification 05000412/LER-2023-003-01, Missile Barrier Door Left Open Resulting in a Loss of Safety Function2024-02-20020 February 2024 Missile Barrier Door Left Open Resulting in a Loss of Safety Function 05000412/LER-2023-004, Condition Prohibited by Technical Specification and Loss of Safety Function Due to Emergency Diesel Generator Lube Oil Contamination by Fuel Oil2023-09-0808 September 2023 Condition Prohibited by Technical Specification and Loss of Safety Function Due to Emergency Diesel Generator Lube Oil Contamination by Fuel Oil 05000412/LER-2023-003, Missile Barrier Door Left Open Resulting in a Loss of Safety Function2023-08-0808 August 2023 Missile Barrier Door Left Open Resulting in a Loss of Safety Function 05000412/LER-2023-002, Automatic Actuation of Auxiliary Feedwater System2023-07-12012 July 2023 Automatic Actuation of Auxiliary Feedwater System 05000412/LER-2023-001, Indications Identified During Reactor Vessel Head Inspection2023-06-16016 June 2023 Indications Identified During Reactor Vessel Head Inspection 05000412/LER-2022-001, Operation or Condition Prohibited by Technical Specification and Loss of Safety Function Due to Emergency Diesel Generator Fuel Oil Intrusion Into Lube Oil2022-09-0808 September 2022 Operation or Condition Prohibited by Technical Specification and Loss of Safety Function Due to Emergency Diesel Generator Fuel Oil Intrusion Into Lube Oil 05000334/LER-2022-001, Manual Reactor Trip and Auxiliary Feedwater Actuation Due to Heater Drain System Valve Failure2022-08-10010 August 2022 Manual Reactor Trip and Auxiliary Feedwater Actuation Due to Heater Drain System Valve Failure 05000412/LER-2021-005, Manual Reactor Trip and Auxiliary Feedwater Actuation Due to Trip of a Main Feedwater Pump2022-01-17017 January 2022 Manual Reactor Trip and Auxiliary Feedwater Actuation Due to Trip of a Main Feedwater Pump 05000412/LER-2021-004, Manual Reactor Trip2022-01-11011 January 2022 Manual Reactor Trip 05000412/LER-2021-003, Indications Identified During Reactor Vessel Head Inspection2021-12-17017 December 2021 Indications Identified During Reactor Vessel Head Inspection 05000412/LER-2021-002, Unit 2, Automatic Reactor Trip and Automatic Actuation of the Auxiliary Feedwater System2021-12-0303 December 2021 Unit 2, Automatic Reactor Trip and Automatic Actuation of the Auxiliary Feedwater System 05000334/LER-2017-0032018-01-0404 January 2018 Beaver Valley Power Station Unit 1 Reactor Trip due to Turbine Trip and Automatic Initiation of the Auxiliary Feedwater System, LER 17-003-00 for Beaver Valley, Unit 1, Regarding Reactor Trip due to Turbine Trip and Automatic Initiation of the Auxiliary Feedwater System 05000334/LER-2017-0022017-09-13013 September 2017 1 OF 4, LER 17-002-00 for Beaver Valley Power Station, Unit No. 1 Regarding Inadequate Emergency Diesel Generator (EOG) Tornado Missile Protection Identified Due to Non-conforming Design Conditions 05000412/LER-2017-0012017-05-0202 May 2017 Surveillance Testing Rendered Service Water System Inoperable Due to the Coupling of Seismic Category 1 Piping to Not Seismic Category 1 Piping, LER 17-001-00 For Beaver Valley Power Station, Unit No. 2 Re: Surveillance Testing Rendered Service Water System Inoperable Due to the Coupling of Seismic Category l Piping to Not Seismic Category 1 Piping 05000334/LER-2017-0012017-04-18018 April 2017 Inadequate Tornado Missile Protection Identified Due to Non-Conforming Design Conditions, LER 17-001-00 for Beaver Valley Power Station, Unit Nos. 1 and 2 Regarding Inadequate Tornado Missile Protection Identified Due to Nonconforming Design Conditions L-08-222, LER 08-01-00 for Beaver Valley, Unit 2, Regarding Unplanned Actuation of the Auxiliary Feedwater System During Plant Startup2008-07-23023 July 2008 LER 08-01-00 for Beaver Valley, Unit 2, Regarding Unplanned Actuation of the Auxiliary Feedwater System During Plant Startup 2024-07-02
[Table view] |
LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification |
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10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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L-24-115 June 6, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 LER 2024-001-00 Beaver Valley Power Station Barry N. Blair Site Vice President P.O. Box4 Shippingport, PA 15077 10 CFR 50.73 Enclosed is Licensee Event Report (LER} 2024-001-00, "Offsite AC Power Source Inoperable due to Breaker Failure Resulting in Condition Prohibited by Technical Specification." This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(B).
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Ms. Hope Gilliam, Manager, Regulatory Compliance, at 724-682-4224.
Barry N. Blair Enclosure: Beaver Valley Power Station, Unit No. 1 LER 2024-001-00 cc: NRG Region I Administrator NRG Senior Resident Inspector NRG Project Manager INPO Records Center (via INPO Industry Reporting and Information System)
BRP/DEP Enclosure L-24-115 Beaver Valley Power Station, Unit No. 1 LER 2024-001-00
Abstract
On April 10, 2024, at 2009 with Beaver Valley Power Station, Unit No. 1 (BVPS-1) at 100 percent power in Mode 1, the incoming supply to the normal 4KV 1A bus from the System Station Service Transformer 1A (SSST), breaker 4KVS-1A-1A4, failed to close when demanded from the control room. At the time, Operators were attempting to transfer the 1A normal 4KV bus to offsite power. The breaker was replaced on April 11, 2024, at 1201 to restore operability. The last time breaker 4KVS-1A-1A4 was manipulated occurred on February 20, 2024, at 2048.
A past operability review of this issue determined the failure likely occurred when the breaker was last closed, prior to this event, on February 18, 2024, at 1217 but remained functional until opened on February 20 at 2048. The cause of the breaker failure was due to a loose charging motor and failure of the motor connecting arm bushing.
This event is reportable as a condition prohibited by technical specifications per 10 CFR 50.73(a)(2)(i)(B).
Energy Industry Identification System (EIIS) codes are identified in the text as [XX].
BACKGROUND The BVPS-1 electric power system [EA] design includes an offsite power system and an onsite power system. During normal operation, BVPS-1 station service power is taken from the unit station service transformer (USST) 1C and 1D [EA-XFMR] or may also be taken from the system station service transformers (SSST) 1A and 1B [EA-XFMR]. Electrical buses may be aligned to one source or the other by manipulating circuit breakers. During normal operation, any one of the USSTs or SSSTs or a combination of both may be selected as the preferred source for operation.
The USSTs receive power from the main unit generator output, and the SSSTs receive power from the 138 KV switchyard.
The 4KV Power Distribution System [EA] provides 4160 VAC power to the various normal and emergency 4KV loads within the station. The system consists of four normal buses 1A, 1B, 1C, 1D [EA-BU] and two emergency buses 1AE, 1DF [EB-BU]. Each bus utilizes two supply breakers, one breaker ties the bus to a secondary winding of the USST, and the other ties it to a secondary of the SSST. Manual transfer from unit to system service supply is accomplished from the control room.
Loss of supply to any bus section automatically trips the source breaker and closes the breaker to the alternate source. A provision is also made for manual transfer.
4KVS-1A-1A4 [EA-BKR] function is to close and provide 4KV power from SSST 1A (offsite) through the normal 1A 4KV bus to emergency bus 1AE following a reactor trip. Breaker 4KVS-1A-1A4 is required to close to meet LCO 3.8.1.
Technical Specification (TS) Limiting Condition for Operation (LCO) 3.8.1 requires two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System and two diesel generators (DGs) capable of supplying the onsite Class 1E power distribution subsystem(s) be OPERABLE in Modes 1, 2, 3, and 4. With one offsite circuit inoperable Condition A requires the offsite circuit be restored to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
DESCRIPTION OF EVENT
On April 10, 2024, at 2009 during manual transfer activities to transfer 1A normal 4KV bus to offsite power, supply breaker 4KVS-1A-1A4 failed to close when demanded from the control room. Train 'A' offsite power was previously declared inoperable at the start of transfer activities on April 10, 2024 at 1919 and remained inoperable until 4KVS-1A-1A4 replacement on April 11, 2024 at 1201. BVPS-1 was in Mode 1 at 100 percent power.
There was no effect to Unit 2 as a result of this event.
CAUSE OF THE EVENT
The direct cause for the 4KVS-1A-1A4 failure to close was the charging motor was loose, motor connecting arm bushing was failed and the power wires were severed, resulting in the inability to charge the springs. A contributing cause is the procedure did not contain adequate guidance for tightening the charging motor.
The charging motor associated with 4KVS-1A-1A4 had been replaced in April 2019 as part of preventative maintenance. The breaker completed 72 open/close operations satisfactorily from April 2019 until its failure on April 10, 2024.
ANALYSIS OF EVENT
This event is reportable as a condition prohibited by technical specifications per 10 CFR 50.73(a)(2)(i)(B) as the Train A offsite power source was inoperable for approximately 50 days.
The plant risk associated with the BVPS-1 failure of normal bus 4KVS-1A supply breaker 4KVS-1A-1A4 is considered to be very low
safety significance
The change in core damage frequency and the change in large early release frequency calculated for the condition are both very small, even with notable conservative assumptions directly relevant to this issue remaining in the PRA model.
A past operability review was completed and determined that the failure likely occurred the last time 4KVS-1A-1A4 was closed on February 18, 2024 at 1217 but remained functional until opened on February 20, 2024, at 2048 resulting in approximately 50 days of inoperability, which exceeded the LCO allowed outage time for Train A offsite power.
A review of operating logs revealed no entries into LCO 3.8.1 Condition A for the redundant offsite power being inoperable concurrently, therefore no loss of safety function.
CORRECTIVE ACTIONS
1)Breaker 4KVS-1A-1A4 was replaced on April 11, 2024.
2)The preventative maintenance procedure for 4 kV breakers was updated to provide more specific guidance on tightening the charging motor, completed on May 30, 2024.
PREVIOUS SIMILIAR EVENTS
No previous similar events were identified.
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05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification | Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation | Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv)(B)(6) 10 CFR 50.73(a)(2)(iv)(B)(1) 10 CFR 50.73(a)(2)(iv)(B)(8) | 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping | Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control | Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control | 10 CFR 50.73(a)(2)(iv)(B)(6) 10 CFR 50.73(a)(2)(iv)(B)(1) |
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