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
MONTHYEARIR 05000416/20240112024-10-16016 October 2024 – Fire Protection Team Inspection Report 05000416/2024011 ML24263A2712024-09-19019 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24257A0172024-09-17017 September 2024 Request for Withholding Information from Public Disclosure Unit 1 IR 05000416/20240122024-09-17017 September 2024 License Renewal Post Approval Phase 2 Inspection Report 05000416/2024012 ML24254A3602024-09-10010 September 2024 Pre-Submittal Slides for License Amendment Request, Criticality Safety Analysis, Technical Specification 4.3.1, Criticality and Technical Specification 5.5.14, Spent Fuel Storage Rack Neutron Absorber Monitoring Program IR 05000416/20244022024-09-0909 September 2024 Security Baseline Inspection Report 05000416/2024402 05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24235A0832024-08-22022 August 2024 Evaluations Performed in Accordance with 10 CFR 50.54(q) for Changes to Emergency Planning Documents IR 05000416/20240052024-08-21021 August 2024 Updated Inspection Plan for Grand Gulf Nuclear Station (Report 05000416/2024005) ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24185A1522024-08-13013 August 2024 Issuance of Amendment Nos. 334, 235, and 215, Respectively, to Revise TSs to Adopt TSTF-205 ML24176A1202024-07-29029 July 2024 Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b IR 05000416/20240022024-07-29029 July 2024 Integrated Inspection Report 05000416/2024002 ML24172A2502024-07-29029 July 2024 – Issuance of Amendment No. 233 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML24204A2432024-07-23023 July 2024 Notification of Cyber Security Baseline Inspection and Request for Information (05000416/2024403) ML24191A2432024-07-0909 July 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operations IR 05000416/20240102024-06-27027 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000416/2024010 ML24156A1762024-06-24024 June 2024 Regulatory Audit Summary in Support of License Amendment Requests to Adopt TSTF-505, Revision 2 and 10 CFR 50.69 (Epids L-2023-LLA-0081 and L-2023-LLA-0080) ML24165A1512024-06-13013 June 2024 Second Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk-Informe ML24163A2652024-06-11011 June 2024 Inservice Inspection Summary Report ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24149A1592024-05-28028 May 2024 Automatic Actuation of Reactor Protection System ML24130A0912024-05-0909 May 2024 Request for Information Letter License Renewal Phase 2 Inspection ML24128A1512024-05-0909 May 2024 Project Manager Assignment ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000416/20240012024-05-0202 May 2024 Integrated Inspection Report 05000416 2024001 ML24122C6112024-05-0101 May 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. ML24116A0372024-04-25025 April 2024 Report of Technical Specification Bases Changes ML24113A0952024-04-22022 April 2024 Annual Radioactive Effluent Release Report for 2023 ML24113A0972024-04-22022 April 2024 Annual Report of Individual Monitoring - NRC Form 5 for 2023 Per 1 0 CFR 20.2206 ML24107B0402024-04-16016 April 2024 Notification by Entergy Operations, Inc., of Proposed Economic Performance Incentive and Reliance on Post-Event Improvements in Plant Procedures And/Or Methods of Operation in FERC ML24107A8872024-04-16016 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24100A0692024-04-0909 April 2024 Report of Changes or Errors to 10 CFR 50.46 Analysis ML24094A0992024-04-0303 April 2024 (GGNS) Core Operating Limits Report (COLR) Cycle 25, Revision O ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams ML24087A1962024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close IR 05000416/20220042024-03-19019 March 2024 – Amended Integrated Inspection Report 05000416/2022004 and Exercise of Enforcement Discretion ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24058A3512024-02-28028 February 2024 Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000416/20230062024-02-28028 February 2024 Annual Assessment Letter for Grand Gulf Nuclear Station - Report 05000416/2023006 IR 05000416/20233012024-02-26026 February 2024 NRC Examination Report 05000416-2023301 ML24043A1892024-02-12012 February 2024 Spent Fuel Storage Radioactive Effluent Release Report for 2023 ML24012A1422024-01-31031 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)) ML24043A0732024-01-29029 January 2024 2024-01 Post Examination Comments IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 IR 05000416/20234012024-01-18018 January 2024 Cyber Security Inspection Report 05000416/2023401 (Public) 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 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000416/LER-2024-003, Feedwater Inlet Check Valve Incorrectly Determined Operable2024-08-26026 August 2024 Feedwater Inlet Check Valve Incorrectly Determined Operable ML24149A1592024-05-28028 May 2024 Automatic Actuation of Reactor Protection System ML24087A1962024-03-27027 March 2024 High Pressure Core Spray Inoperable Due to Minimum Flow Valve Failure to Close ML23334A0512023-11-30030 November 2023 Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification 05000416/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 2024-08-26
[Table view] |
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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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