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Category:Letter
MONTHYEARML24278A2832024-11-0707 November 2024 Letter to E. Carr Environmental Impact Statement Scoping Summary Report for Virgil C. Summer Nuclear Station Unit 1 ML24305A1302024-10-31031 October 2024 Submittal of 30 Day Report Per 10 CFR 26.719(c) Blind Performance Testing ML24308A0052024-10-28028 October 2024 10-28-24 NRC V.C. Summer Nuclear Station SLR Cherokee Nation Letter to USNRC ML24308A0062024-10-25025 October 2024 Subsequent License Renewal Application Area of Potential Effect (Ape) Clarification Fairfield County, South Carolina SHPO Project No. 22-EJ0147 ML24302A1442024-10-24024 October 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 4 and Requested Information Formation in Response to Limited Aging Management Audit ML24250A0782024-10-22022 October 2024 Relief Request RR-5-V1 Regarding Service Water Return Header Check Valves ML24256A2322024-10-22022 October 2024 Relief Request RR-5-P1 Charging/Safety Injection Pumps ML24255A3152024-10-22022 October 2024 Relief Request RR-5-V2 Regarding Pressure Isolation Valves 05000395/LER-2024-002, Loss of Control Room Emergency Filtration System2024-10-15015 October 2024 Loss of Control Room Emergency Filtration System ML24290A1052024-10-0707 October 2024 Core Operating Limits Report VCSNS Unit 1 Cycle 29, Revision 0 IR 05000395/20244042024-09-26026 September 2024 Cyber Security Inspection Report 05000395-2024404 - Public ML24274A1942024-09-26026 September 2024 (Vcsns), Unit 1 Subsequent License Renewal Application (SLRA) First 10 CFR 54.21(b) Annual Amendment ML24221A2112024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0552024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0642024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0542024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) ML24267A0592024-09-23023 September 2024 Clarification Regarding Area of Potential Effect for the Subsequent Operating License Renewal for Virgil C. Summer Nuclear Station Fairfield County, South Carolina (SHPO Project Number: 22-EJ0147) (Docket Number: 50-395) IR 05000395/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000395/2024402 IR 05000395/20240052024-08-22022 August 2024 Updated Inspection Plan for Virgil C. Summer Nuclear Station - Report 05000395/2024005 ML24190A4012024-08-19019 August 2024 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Dominion Energy Letter Dated May 30, 2024 IR 05000395/20240022024-08-12012 August 2024 Integrated Inspection Report 05000395/2024002 ML24180A0062024-08-0505 August 2024 Issuance of Amendment No. 227 to Modify Technical Specification 3.8.3.1 to Increase Completion Time for 120-Volt A.C. Vital Busses ML24218A3002024-08-0101 August 2024 Environmental Review Response to NRC Requests for Additional Information and Response to NRC Requests for Confirmation of Information Set 1 ML24158A3882024-07-31031 July 2024 Issuance of Amendment No. 226 to Change Emergency Plan Staff Augmentation Times and Relocate Emergency Operations Facility ML24162A3292024-07-0505 July 2024 Letter to E Carr - V.C. Summer Unit 1 - Summary of the May 2024 Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24185A1902024-06-25025 June 2024 Submittal of Updated Final Safety Analysis Report, Revision 24 ML24177A1382024-06-25025 June 2024 Aging Management Audit Report- VC Summer, Unit 1 - Subsequent License Renewal Application ML24178A1192024-06-25025 June 2024 Update to License Amendment Request- Inverter Allowed Outage Time (AOT) Extension ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24171A0152024-06-17017 June 2024 Update to Subsequent License Renewal Application (SLRA) Response to NRC Request for Additional Information Set 2 Safety Review ML24157A3352024-06-0606 June 2024 – Notification of an NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000395-2024404 and Request for Information ML24155A2042024-05-31031 May 2024 Proposed Alternative Request RR-24-123, Containment Unbonded Post-Tensioning System Inservice Inspection Requirements ML24155A1462024-05-30030 May 2024 Update to Subsequent License Renewal Application (SLRA) -Response to NRC Request for Additional Information Set 1 Response to NRC Request for Confirmation of Information Set 1 and Supplement 3 ML24143A1792024-05-22022 May 2024 Special Report 2024-001-01 for Virgil C. Summer Nuclear Station (Vcsns), Unit 1, Waste Gas System Inoperability ML24141A2822024-05-20020 May 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes IR 05000395/20240012024-05-10010 May 2024 Integrated Inspection Report 05000395/2024001 ML24129A2002024-05-0606 May 2024 Update to Subsequent License Renewal Application, Supplement 2 IR 05000395/20240402024-05-0101 May 2024 95001 Supplemental Inspection Report 05000395/2024040 and Follow-Up Assessment Letter ML24121A1002024-04-29029 April 2024 Response to Request for Additional Information Regarding Alternative Request RR-5-V2 ML24120A2072024-04-29029 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24116A2052024-04-23023 April 2024 Annual Radioactive Effluent Release Report ML24109A1792024-04-19019 April 2024 Aging Management Audit Plan Regarding the Subsequent License Renewal Application Review ML24108A0392024-04-18018 April 2024 Letter to E Carr-V.C. Summer Unit 1- Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application ML24108A0672024-04-17017 April 2024 Submittal of Summary for Condition of the Service Water Intake Structure Provided in Accordance with License Condition 2.C.5.d 05000395/LER-2024-001, (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator2024-04-17017 April 2024 (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator ML24100A7312024-04-0909 April 2024 Personnel Exposure and Monitoring Annual Report ML24095A2072024-04-0101 April 2024 Update to Subsequent License Renewal Application (SLRA) Supplement 1 ML24088A2062024-03-26026 March 2024 Annual Operating Report ML24087A2182024-03-26026 March 2024 (Vcsns), Unit 1 - License Amendment Request - Emergency Response Organization (ERO) Augmentation Time Change, Emergency Operations Facility Relocation and Other Emergency Plan Changes - Response to Request. 2024-09-26
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000395/LER-2024-002, Loss of Control Room Emergency Filtration System2024-10-15015 October 2024 Loss of Control Room Emergency Filtration System 05000395/LER-2024-001, (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator2024-04-17017 April 2024 (Vcsns), Unit 1, Automatic Actuation of B Emergency Diesel Generator 05000395/LER-2023-001, Manual Reactor Trip Due to Loss of Main Feedwater Pump2023-05-30030 May 2023 Manual Reactor Trip Due to Loss of Main Feedwater Pump 05000395/LER-2022-001-01, (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault2022-12-15015 December 2022 (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault 05000395/LER-2022-002-01, Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator2022-12-0808 December 2022 Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator 05000395/LER-2022-002, (Vcsns), Unit 1, Potential Condition Prohibited by Technical Specification 3.8.1.12022-04-11011 April 2022 (Vcsns), Unit 1, Potential Condition Prohibited by Technical Specification 3.8.1.1 05000395/LER-2021-001-01, Condition Prohibited by Technical Specifications2022-02-0808 February 2022 Condition Prohibited by Technical Specifications 05000395/LER-2022-001, (VCSNS) Unit 1, Manual Reactor Trip Due to Main Transformer Fault2022-01-14014 January 2022 (VCSNS) Unit 1, Manual Reactor Trip Due to Main Transformer Fault 05000395/LER-2021-001, (Vcsns), Unit 1, Condition Prohibited by Technical Specifications2021-08-26026 August 2021 (Vcsns), Unit 1, Condition Prohibited by Technical Specifications RC-18-0049, LER 2018-001-01 Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator2018-05-0707 May 2018 LER 2018-001-01 Tor Virgil C. Summer, Unit 1, Valid Actuation of Emergency Diesel Generator RC-18-0056, (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors2018-04-25025 April 2018 (Vcsns), Unit 1 - Licensee Event Reports (2016-001-02, 2016-002-01, 2016-003-02) - Revision to Correct Typographical Errors 05000395/LER-2017-0052017-12-22022 December 2017 AUTOMATIC REACTOR TRIP DUE TO MAIN TURBINE TRIP, LER 17-005-00 for V.C Summer, Unit 1, Regarding Automatic Reactor Trip Due to Main Turbine Trip 05000395/LER-2017-0062017-12-15015 December 2017 TECHNICAL SPECIFICATION ACTION NOT MET FOR INOPERABLE OXYGEN MONITOR, LER 17-006-00 for Virgil C. Summer, Unit 1, Regarding Technical Specification Action not Met for Inoperable Oxygen Monitor 05000395/LER-2017-0032017-10-26026 October 2017 FAILED LIGHTNING ARRESTER ON MAIN TRANSFORMER CAUSES REACTOR TRIP, LER 17-003-00 For Virgil C. Summer Nuclear Station, Unit 1, Regarding Failed Lightning Arrester On Main Transformer Causes Reactor Trip 05000395/LER-2017-0022017-08-25025 August 2017 Low Feedwater Flow to the 'B' Steam Generator Causes Automatic Reactor Trip, LER 17-002-00 for V.C. Summer, Unit 1, Regarding Low Feedwater Flow to the 'B' Steam Generator Causes Automatic Reactor Trip 05000395/LER-2017-0012017-07-24024 July 2017 C MAIN FFFDWATER PUMP FAILURE '1'0 TRIP RESUI,TS IN LOSS OF EMERGENCY FE,EDWATER AUTO START ACTUATION SIGNAL, LER 17-001-00 for V.C. Summer, Unit 1, Regarding C Main Feedwater Failure to Trip Results in Loss of Emergency Feedwater Auto Start Actuation Signal RC-15-0190, Special Report (Spr) 2014-005-01, Loss or Theft of License Material2015-12-16016 December 2015 Special Report (Spr) 2014-005-01, Loss or Theft of License Material RC-15-0179, Special Report (Spr) 2015-002 Regarding One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days2015-11-0303 November 2015 Special Report (Spr) 2015-002 Regarding One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days RC-15-0139, Submittal of Special Report (Spr) 2015-001 Regarding the Loose-Part Monitoring System (Lpms) Channel Number 8 Being Inoperable in Excess of 30 Days2015-08-20020 August 2015 Submittal of Special Report (Spr) 2015-001 Regarding the Loose-Part Monitoring System (Lpms) Channel Number 8 Being Inoperable in Excess of 30 Days RC-14-0084, Special Report 2014-003 for V.C. Summer, One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days2014-05-14014 May 2014 Special Report 2014-003 for V.C. Summer, One or More Required Meteorological Monitoring Channels Being Inoperable for More than Seven (7) Days RC-14-0085, Special Report 2014-002 for V.C. Summer, Degraded Conditions Lasting Longer than Seven Days2014-05-14014 May 2014 Special Report 2014-002 for V.C. Summer, Degraded Conditions Lasting Longer than Seven Days ML12334A4432012-11-27027 November 2012 SR 12-002-00 for Virgil C. Summer, Unit 1 Regarding Meteorological Monitoring Channels Being Inoperable for More than Seven Days ML12188A5422012-07-0303 July 2012 Special Report 2012-001 ML12079A2862012-03-16016 March 2012 LER 12-01-00 for Virgil C. Summer, Unit 1 Regarding Core Exit Thermocouples Inoperable Due to an Inadequate Maintenance Procedure ML11186A9742011-06-30030 June 2011 Regarding Depressurization of the 'C' Steam Line Creating a Differential Pressure Greater than 97 PSIG Between the Steam Lines, Initiating a Safety Injection ML11117A3042011-04-25025 April 2011 V. C. Summer, Unit 1, Submittal of Special Report (Spr) 2011-001 Re Control Building Fire/Pressure Door (DRCB/102) Being Inoperable for Greater than Seven Days Prior to Completing Repair of the Door ML0614201452006-05-17017 May 2006 LER 99-014-03 for Virgil C. Summer Nuclear Station, Re Kaowool Fire Barriers Outside 10 CFR 50 Appendix R Design Basis RC-06-0051, Special Report (Spr) 2006-002 - Inoperability of the Main Steam Line Radiation Monitors (RMG-1 9A(B)(C)) for Greater than 72 Hours2006-03-13013 March 2006 Special Report (Spr) 2006-002 - Inoperability of the Main Steam Line Radiation Monitors (RMG-1 9A(B)(C)) for Greater than 72 Hours ML0527803362005-09-28028 September 2005 LER 05-S01-01 for Virgil C. Summer Nuclear Station Regarding Entry of Unauthorized Employee Into the Protected Area RC-05-0095, LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area2005-06-22022 June 2005 LER 05-S01-00 for Virgil C. Summer Nuclear Station Entry of Unauthorized Employee Into the Protected Area ML0335001292003-12-11011 December 2003 LER 03-S03-00 for Virgil C. Summer Regarding Access to Protected Area by an Individual Without Proper Authorization ML0326605072003-09-16016 September 2003 LER 03-S02-00 for Virgil C. Summer Regarding Access to Protected Area by an Individual with Expired Training ML0318404692003-07-0101 July 2003 LER 99-014-02, Virgil C. Summer Re Kaowool Fire Barriers Outside 10CFR50 Appendix R Design Basis ML0308605122003-03-20020 March 2003 LER 03-S01-00 from Summer Regarding Access to Protected Area by an Individual with an Expired Badge 2024-04-17
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LER-2022-001, (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault |
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V.C. Summer Nuclear Station ~ Dominion Bradham Blvd & Hwy 215, Jenkinsville, SC 29065 Mailing Address: ~ Energy P.O. Box 88, Jen kinsville, SC 29065 DominionEnergy.com December 15, 2022
Document Control Desk Serial No. : 22-001A U.S. Nuclear Regulatory Commission VCS-LIC/HK RO Washington, DC 20555 Docket No. 50-395 License No. NPF-12
DOMINION ENERGY SOUTH CAROLINA (DESC)
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 LICENSEE EVENT REPORT 2022-001-01 MANUAL REACTOR TRIP DUE TO MAIN TRANSFORMER FAULT
Dominion Energy South Carolina hereby submits Licensee Event Report (LER) 2022-001-01, for VCSNS. This report provides updated details concerning a manual reactor trip due to a main transformer fault and is submitted in accordance with 10 CFR 50. 73(a)(2)(iv)(A).
Should you have any questions, please call Mr. Michael Moore at (803) 345-4752.
Sincerely,
~~
George A. Lippard Site Vice President V.C. Summer Nuclear Station
Enclosure
Commitments contained in this letter: None
cc:
G. J. Lindamood - Santee Cooper L. Dudes - NRC Region II G. Miller - NRC Project Mgr.
NRC Resident Inspector J. N. Bassett-INPO Marsh USA, Inc.
Abstract
On November 15, 2021, at approximately 1728 EST with Unit 1 in Mode 1 at 47 percent power, the reactor was manually tripped due to a fault on the 8-phase of the main transformer. The turbine tripped automatically based on the reactor trip signal.
Emergency Feedwater (EFW) actuation occurred as expected due to the low-low steam generator water levels which occurred as a result of the reactor trip. The reactor trip was not complex with all systems responding normally post trip. Operations stabilized the plant in Mode 3. Decay heat was removed by the steam generators, utilizing the steam dump system.
Due to the manual Reactor Protection System (RPS) actuation and the automatic actuation of the EFW system, this event is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(A).
1.0 DESCRIPTION OF THE EVENT
On November 14, 2021, at approximately 1141 EST, VCSNS closed the main generator breaker, conclud ing refueling outage 26. Normal startup was in progress. On November 15, 2021, at approximately 1728 EST with Unit 1 in Mode 1 at 47 percent power, the reactor was manually tripped due to a fault on the 8 -phase of the main transformer (XTF0001). The turbine tripped automatically based on the reactor trip signal. Eme rgency Feedwater (EFW) actuation occurred as expected due to the low - low steam generator water levels which occurred as a result of the reactor trip. The reactor trip was not complex with all systems responding normally post trip. Operations stabilized the plant in Mode 3. Decay he at was removed by the steam gen e rators, utilizing the steam dump system.
There were no other structures, system s, or components (SSCs) tha t were inoperable at the beginning of the even t o r contributed to the event.
Due to the manual Reactor Protection System (RPS) actuation and the automatic actuation of the EFW system, this e vent is being reported in accordance with 10 CFR 50.73(a)(2)(iv)(A).
2.0 SIGNIFICANT SAF ETY CONSEQUENCES AND IMPLICATIONS
XTF0001 serves no safety related purpose for the unit. When the transfo rmer failed, all of the appropriate safety systems responded as designed. The main generator, turbine, reactor, and EFW system operated as expected ; and all the control rods fully inserted into the core. The operating crew performed as expected. The event was with in the analysis of the Updated Final Safety Analysis Report Chapter 15. This event did not pose a threat to the health and safety of the public.
Therefore, the safety significance of this issue is very low.
3.0 CAUSE OF THE EVENT
The fault was caused by a failure of the center phase high-voltage bushing. Substantial evidence supports that an electrical failure occurred inside the bushing itself. Failure analysis indicates that it is most probable that the H2 bushing failed due to one or mo re manufacturing defects. Specifically, erroneous layers of paper insulation and a large surface defect on the conductor.
4.0 IMMEDIATE CORRECTIVE ACTIONS
The faulted transformer was removed from service and replaced with the spare ma in transformer. The unit was placed back online with breakers closed on December 10, 2021.
5.0 ADDITIONAL CORRECTIVE ACTIONS
None
6.0 ACTIONS TO PREVENT RECURRENCE
A new high voltage composite bushing design was selected to be utilized in the new replacement transformer design.
A vendor surveillance plan for the manufacturing and testing of the high voltage bushings for the replacement transformer is being developed and will be implemented to provide confidence that manufacturing defects are identified and addressed prior to installation.
7.0 SIMILAR EVENTS
On August 28, 2017, VCSNS Unit 1 automatically tripped due to a turbine trip. The turbine trip was caused by the Main Generator Differential Lockout due to a fault on the center phase, 230 kV lightning arrester, on the main transformer. This is described in LER 2017-003-01 (ML17347A216).
8.0 MANUFACTURER/PURCHASE ORDER NUMBER
The failed center phase high-voltage bushing was manufactured by ABB and is an ABB O+C 230kV 900kV BIL 4000A oil impregnated bushing.
The main transformer was manufactured by Mitsubishi Electric Corporation. The Mitsubishi Design Number is HE11343.
The transformer was purchased under P.O. Number NU-02NN728893.
9.0 ADDITIONAL INFORMATION
None
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05000395/LER-2022-001-01, (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault | (Vcsn), Unit 1, Manual Reactor Trip Due to Main Transformer Fault | | 05000395/LER-2022-001, (VCSNS) Unit 1, Manual Reactor Trip Due to Main Transformer Fault | (VCSNS) Unit 1, Manual Reactor Trip Due to Main Transformer Fault | | 05000395/LER-2022-002-01, Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator | Condition Prohibited by Technical Specifications: Inoperable B Emergency Diesel Generator | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000395/LER-2022-002, (Vcsns), Unit 1, Potential Condition Prohibited by Technical Specification 3.8.1.1 | (Vcsns), Unit 1, Potential Condition Prohibited by Technical Specification 3.8.1.1 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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