05-16-2016 | At 1515 [CDT] on March 17, 2016, with Unit 1 in Mode 5 for a refueling outage, Grand Gulf Nuclear Station ( GGNS) experienced an electrical fault and subsequent undervoltage condition on the 115kV offsite power source supplying the onsite Division 2 Engineered Safety Feature ( ESF) transformer, ESF 12, and bus. The fault was present long enough to cause an actuation of the Division 2 Load Shedding and Sequencing ( LSS) System and subsequent start of the Division 2 Standby Diesel Generator (SDG). The in-service B train of Residual Heat Removal ( RHR) was load shed, as designed, and, within 7 seconds, the Division 2 SDG restored power to the Division 2 bus. RHR B was restored within 3 minutes and 13 seconds. Core alterations, in progress at the time, were suspended and fuel bundles were placed in their proper positions. The ESF 11 transformer was paralleled with SDG 2. The Division 2 bus was then placed back to the ESF 11 offsite electrical feed and the Division 2 SDG was secured. The apparent cause was determined to be that the 115kV line was not equipped with pilot scheme protective relaying. Protective relaying is scheduled to be installed in 2017.
Alternate Heat Decay Removal (ADHR) remained available throughout this time period. No changes in Spent Fuel Pool or Reactor Cavity temperature were observed. All safety systems operated as expected for the loss of power to ESF12 and Division 2 LSS System.
The automatic start of the Division 2 Standby Diesel Generator is being reported pursuant to 10 CFR 50.73(a)(2)(iv)(A) and the temporary loss of RHR ( Shutdown Cooling) is being reported pursuant to 10 CFR 50.73(a)(2)(v)(B). |
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Category:Letter
MONTHYEARML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000416/20234032023-11-13013 November 2023 Security Baseline Inspection Report 05000416/2023403 Cover Letter ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000416/20230032023-11-0808 November 2023 Integrated Inspection Report 05000416/2023003 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23270B1892023-09-27027 September 2023 Evacuation Time Estimate Study ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure ML23240A3952023-08-28028 August 2023 Reply to a Notice of Violation; EA-23-019 IR 05000416/20230052023-08-21021 August 2023 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2023005) ML23226A1002023-08-18018 August 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF-505, Revision 2, and 10 CFR 50.69 IR 05000416/20230022023-08-0808 August 2023 Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001 IR 05000416/20234042023-08-0707 August 2023 Material Control and Accounting Program Inspection Report 05000416/2023404 IR 05000416/20230912023-07-28028 July 2023 Final Significance Determination of a Green Finding and Notice of Violation; NRC Inspection Report 05000416/2023091 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23166B0712023-06-15015 June 2023 Reply to Notice of Violation EA-22-104 and EA-22-115 ML23166B0662023-06-15015 June 2023 Response to NRC Integrated Inspection Report 05000416/2023001 ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) GNRO-2023/00014, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0606 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GNRO-2023/00015, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-06-0606 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23122A1632023-05-18018 May 2023 NRC Inspection Report 05000416/2023090 and Preliminary White Finding IR 05000416/20234022023-05-17017 May 2023 Security Baseline Inspection Report 05000416/2023402 ML23110A8002023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000416/20230012023-05-10010 May 2023 Notice of Violation; Integrated Inspection Report 05000416/2023001 and NRC Investigation Report 4-2022-004 ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23117A0422023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) ML23111A2132023-04-21021 April 2023 Responses to RAI Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities ML23110A1122023-04-20020 April 2023 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML23110A0552023-04-20020 April 2023 Annual Radiological Environmental Operating Report (AREOR) ML23103A1022023-04-13013 April 2023 Annual Report of Individual Monitoring - NRC Form 5 for 2022 Per 10 CFR 20.2206 ML23102A1482023-04-12012 April 2023 Notification of NRC Initial Operator Licensing Examination 05000416/2024301 ML23089A0602023-03-30030 March 2023 Entergy Operations, Inc. - Fleet Project Manager Assignment ML23088A3922023-03-29029 March 2023 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML23079A2772023-03-21021 March 2023 U.S. Nuclear Regulatory Commission Presentation at the May 1, 2023, Port Gibson City Council Meeting ML23080A2882023-03-21021 March 2023 Decommissioning Funding Status Report Per 10 CFR 50.75(f)(1) Entergy Operations, Inc IR 05000416/20230112023-03-0808 March 2023 Design Basis Assurance Inspection Report 05000416/2023011 2024-01-31
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000416/LER-2016-0092017-08-16016 August 2017 Entry into Mode of Applicability with the Oscillation Power Range Monitor Upscale Settings Incorrectly Set, LER 16-009-01 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set 05000416/LER-2016-0082017-08-16016 August 2017 Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable, LER 16-008-001 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable 05000416/LER-2017-0012017-03-28028 March 2017 High Pressure Core Spray (HPCS) Jockey Pump Trip, LER 17-001-00 for Grand Gulf, Unit 1, Regarding High Pressure Core Spray Jockey Pump Trip 05000416/LER-2016-0012016-05-16016 May 2016 Valid Engineered Safety Feature Actuation and Temporary Loss of Residual Heat Removal, LER 16-001-00 for Grand Gulf, Unit 1, Regarding Valid Engineered Safety Feature Actuation and Temporary Loss of Residual Heat Removal GNRO-2014/00049, Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package, Revision 112014-07-31031 July 2014 Report Pursuant to 10 CFR 71.95 (a)(3) and (B) of Seven Potential Instances of Noncompliance with Certificate of Compliance No. 9233 for TN-RAM Package, Revision 11 ML12157A1822012-05-23023 May 2012 Attachment 9 to GNRO-2012/00039 - Entergy Nuclear Grand Gulf Nuclear Station License Renewal Environmental Audit - Hydrology Patton - Attachment L Labeled Reporting Documentation - Unit 2 Sumps. ML0627100452005-08-22022 August 2005 Final Precursor Analysis - Grand Gulf, Unit 1 2017-08-16
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3. LER NUMBER
001 0 05000- A. Initial Conditions:
At the time of the event, Grand Gulf Nuclear Station (GGNS) was in Mode 5 for Refueling Outage RF20. The station was in a shutdown condition with the reactor cavity flooded and the spent fuel pool gates not installed. System lineups were as follows:
- Engineered Safety Feature (ESF) Transformers [XFMR], ESF 11 and ESF 12, were available from offsite electrical feeders - Division 1 bus was being supplied by ESF 11 - Division 2 and 3 buses were being supplied by ESF 12 - Division 1 and Division 2 Standby Diesel Generators (SDGs) [EK] were available for onsite electrical feeders - Residual Heat Removal (RHR) [BO] 'B' was in Shutdown Cooling mode supplied by the Division 2 bus - Alternate Decay Heat Removal (ADHR) was available
B. Description of Events:
At approximately 15:15, on March 17, 2016, an electrical fault occurred on the 115kV feeder supplying the GGNS ESF 12 transformer. The fault caused an undervoltage condition in the GGNS switchyard which was present long enough to generate a valid actuation signal to the Division 2 Load Shedding and Sequencing (LSS) [JE] System and the Division 2 Standby Diesel Generator (SDG). RHR 'B' was load shed and the Division 2 SDG started. The SDG automatically sequenced to the Division 2 bus, restoring power as designed, within 7 seconds. Core alterations, in progress at the time, were suspended and fuel bundles were placed in their proper positions. RHR 'B' was restored by SDG 2 within 3 minutes and 13 seconds. The ESF 11 transformer was then paralleled with SDG 2. The Division 2 bus was then placed back to the ESF 11 offsite electrical feed and the Division 2 SDG was secured. ADHR remained available throughout the event and no changes in Spent Fuel Pool or Reactor Cavity temperature were observed.
Severe weather was present at the time of the event and high winds were suspected to have initiated the transient. Transmission personnel performed a walkdown and investigation of the Baxter Wilson to Port Gibson 115kV transmission line. In an area where the 115kV transmission line crosses an 8kV distribution line, burn marks were identified on two of the three phase conductors ('A' and 'B' phases). The lines either came into contact with one another or came within close proximity to one another. A subsequent review of the data recorded during the event revealed that there was initially a single phase fault ('B' to phase-to-ground) and evolved into a phase-to-phase fault ('A' phase-to-'B' phase-to-ground). This was determined to be the direct cause of the event.
The Port Gibson switchyard is fed from both the Baxter Wilson and Natchez transmission lines. Due to the location of the fault on the Baxter Wilson line, 2.1 miles from Baxter Wilson, and the current protective relaying design, the Baxter Wilson breaker opened instantaneously (zone 1 fault). Opening of the Port Gibson breaker is delayed 30 cycles (-0.5 seconds), per design, for the given fault distance (zone 2). After the fault was present for the required 30 cycles, the breaker opened within 5-6 cycles. In total, the fault was present on the line for .58 seconds. With the Natchez line feeding the Port Gibson switchyard, the fault caused the yard voltage to drop approximately 21 kV phase-to-ground (-31% of the nominal 67kV phase-to-ground) for the duration of the fault until the Port Gibson breaker opened. Although the feeder from the Port Gibson yard to GGNS remained intact, this degraded voltage condition was detected by the Division 2 LSSS which load shed and, in turn, initiated the ESF actuation .46 seconds later. All onsite and offsite equipment operated as expected for the current design. GGNS personnel responded in accordance with Off Normal Event Procedures and appropriate actions were taken.
The apparent cause was determined to be that the Baxter Wilson to Port Gibson 115kV line does not have pilot scheme protection. The phase-to-phase fault would have cleared sooner with protective relaying. A project is planned, in 2017, to upgrade the Baxter Wilson to Port Gibson transmission line with a fiber optic pilot scheme.
Event Notification No. 51800 was made to the NRC Operations Center for both the declaration of a valid ESF actuation and a loss of Shutdown Cooling in accordance with 10CFR50.72(b)(3)(iv)(A) and 10CFR50.72(b)(3)(v)(B), respectively.
C. Cause of Event:
The apparent cause was determined to be that the Baxter Wilson to Port Gibson line does not have pilot scheme protection. The phase- to-phase fault would have cleared sooner with protective relaying.
D. Extent of Condition:
A ground fault similar to the one described here could potentially occur on any of the four qualified GGNS electrical feeder lines.
Investigation revealed that the Baxter Wilson line is the only line that experiences a delayed breaker clearing upon receipt of a ground fault condition. The other three lines are all protected by pilot scheme protective relaying which allows for nearly instantaneous clearing which would prevent actuation of load shedding on a perceived loss of offsite power. It was also determined that, in order for the event described here to occur, the ground fault would have had to be at a distance greater than 80% of the the way from Port Gibson to Baxter Wilson, which was the case. Implementation of pilot scheme protective relaying would also prevent actuation of load shedding anywhere that a ground fault occurs on the line.
E. Corrective Actions:
The immediate action was to clear the fault and re-energize the Baxter Wilson to Port Gibson 115kV line.
A longer term corrective action is to implement pilot scheme protective relaying. Work is planned and expected to be completed in July of 2017.
F. Previous Similar Events:
CR-GGN-2003-1128 documented an event in April of 2003 where a fault occurred on the 115kV Natchez to Port Gibson line during severe weather. The fault occurred between the Port Gibson substation and GGNS, at a distance that would have allowed nearly instantaneous clearing of the Port Gibson breaker. At the time of the fault, no plant equipment was being supplied by the Natchez line.
The line was re-energized and no further corrections were initiated. Because of the location of the fault, the fact that the plant was not being supplied by the Natchez line and the fact that there was no plant response, this event would not have been a learning for GGNS.
Also, of note, the Natchez line now has pilot scheme protection.
F. Safety Significance:
At the time of the event, GGNS Unit 1 was in Mode 5 for a Refueling Outage. The Division 2 LSSS and SDG automatically load shed and re-energized the Division 2 bus. Shutdown Cooling was temporarily lost but was returned within 3 minutes and 13 seconds.
ADHR was available for the duration of the event. All systems operated as designed and GGNS personnel took appropriate actions.
There was no change in Spent Fuel Pool or Reactor Cavity temperature. The Unit remained in Mode 5 and offsite power was restored.
The safety significance is considered to be low and there were no actual nuclear safety consequences.
G. Basis of Reportability:
This LER is being submitted pursuant to Title 10 Code of Federal Regulations 10 CFR 50.73(a)(2)(iv)(A) for the actuation of an Engineered Safety Feature (SDG) and 10 CFR 50.73(a)(2)(v)(B) temporary loss of RHR (Shutdown Cooling).
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05000416/LER-2016-001 | Valid Engineered Safety Feature Actuation and Temporary Loss of Residual Heat Removal LER 16-001-00 for Grand Gulf, Unit 1, Regarding Valid Engineered Safety Feature Actuation and Temporary Loss of Residual Heat Removal | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | 05000416/LER-2016-002 | Automatic Actuation of the Reactor Protection System due to 'B' Main Transformer Wiring | | 05000416/LER-2016-003 | Loss of Secondary Containment Safety Function During Routine Roof Inspection | 10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material | 05000416/LER-2016-004 | Automatic Reactor SCRAM during Turbine Stop and Control Valve Surveillance | | 05000416/LER-2016-005 | Automatic Reactor SCRAM | | 05000416/LER-2016-006 | Multiple Valid Engineered Safety Feature Actuations | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000416/LER-2016-007 | Technical Specification Shutdown due to Loss of Residual Heat Removal Pump | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000416/LER-2016-008 | Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable LER 16-008-001 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable | | 05000416/LER-2016-009 | Entry into Mode of Applicability with the Oscillation Power Range Monitor Upscale Settings Incorrectly Set LER 16-009-01 for Grand Gulf, Unit 1, Regarding Entry into Mode of Applicability with the OPRM Upscale Settings Incorrectly Set | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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