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Category:Letter
MONTHYEARML24025A0922024-01-25025 January 2024 Requalification Program Inspection L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) ML23263A0192023-09-20020 September 2023 Operator Licensing Examination Approval ML23243A9272023-09-19019 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000334/20230052023-08-31031 August 2023 Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005) L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000334/20230022023-08-0909 August 2023 Integrated Inspection Report 05000334/2023002 and 05000412/2023002 ML23219A0592023-08-0707 August 2023 Steam Generator Inspection Reports - Spring 2023 Spring Refueling Outrage L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23188A0672023-07-10010 July 2023 Project Manager Assignment L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report ML23157A1072023-06-0707 June 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000334/2023011 and 05000412/2023011 ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 ML23102A1472023-05-22022 May 2023 Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23135A7872023-05-19019 May 2023 Summary of Conference Calls Regarding the Spring 2023 Steam Generator Tube Inspections L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report ML23124A3882023-05-16016 May 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Technical Specification 5.6.3, Core Operating Limits Reports (COLR) and TS 4.2.1 Fuel Assemblies ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000334/20230012023-05-0808 May 2023 Integrated Inspection Report 05000334/2023001 and 05000412/2023001 L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23118A3812023-04-28028 April 2023 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23107A2502023-04-18018 April 2023 Requalification Program Inspection 2024-01-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000334/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 2018-01-04
[Table view] |
comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
05000- Beaver Valley Power Station Unit Number 1 334 Energy Industry Identification System (EIIS) codes identified in the text as [XX].
CONDITIONS PRIOR TO OCCURENCE
Beaver Valley Power Station Unit 1 (BV-1) was in Mode 1 at 100% Power There were no Structures, Systems, or Components (SSCs) that were inoperable at the start of the event that contributed to the event.
DESCRIPTION OF EVENT
On November 7, 2017, at 05:04 EST, BV-1 experienced an automatic Reactor Trip due to an automatic Turbine [TRB] Trip initiated by a Main Unit Generator [MG] over-current protection [51] relay [RLY] actuation. The reactor trip was without complications, with safety related equipment performing their required functions to place and maintain the plant in Mode 3.
All control rods [AA] fully inserted into the reactor core. The Auxiliary Feedwater System [BA] automatically actuated on low Steam Generator [SG] Water Level as expected, and performed as designed. The plant was stabilized in Mode 3 with the normal Main Feedwater System [SJ] in service and the Auxiliary Feedwater System properly secured. Post trip response addressed an issue with both source range detectors [JI] which had no impact on maintaining the plant in Mode 3.
CAUSE OF EVENT
The Direct Technical Cause of this event was conductive foreign material in the isophase bus duct. The foreign material was found during an inspection of the Main Unit Generator Isophase Bus [BU] Duct Cooling System. The foreign material caused an electrical ground fault which led to the generator protection trip and subsequent turbine trip and reactor trip.
High Potential (Hi-Pot) testing was performed on all three phases of the bus, confirming that the "B" phase was faulted.
In 2013, a full bus duct inspection was to be completed but the scope was changed and only a partial bus duct inspection was performed. The Root Cause was determined to be, "individuals made decisions in 2013 that allowed personnel to change the work scope, without following the process to get approval for the change in work scope".
The contributing cause was that the procedure to perform the bus duct inspections was unclear as to what constituted a "full" inspection and if such a "full" inspection was required. The lack of clarity in the procedure created a "weak barrier" and contributed to confusion on the part of the workers.
comments regarding burden estimate to the Information Services Branch (T-2 F43), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
05000- Beaver Valley Power Station Unit Number 1 334
ANALYSIS OF EVENT
The plant risk associated with the BVPS Unit 1 reactor trip and automatic auxiliary feedwater actuation due to a turbine trip on November 7, 2017 is considered to be very low. This is based on the change in average core damage frequency derived using conditional large early release probability for this event.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(iv)(A) as a condition that resulted in the automatic actuation of the Reactor Protection System (RPS) and the expected automatic actuation of the Auxiliary Feedwater System.
CORRECTIVE ACTIONS
1. The BVPS Unit 1 isophase bus ducts have been properly inspected and cleared of all foreign material. (Complete) 2. In order to preclude recurrence, the inspection procedure is being revised to clearly state the requirement to perform a full isophase bus duct inspection.
Completion of item 2 listed above is being tracked in the Corrective Action Program.
PREVIOUS SIMILAR EVENTS
A review of the previous three years identified the following similar event:
BV-1 LER 2014-001-01 "Beaver Valley Unit 1 Trip due to Main Unit Transformer Failure".
CR 2017-11134, 11215
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05000412/LER-2017-001 | 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 | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000334/LER-2017-001 | 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 | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000334/LER-2017-002 | 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 | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000334/LER-2017-003 | 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 | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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