12-07-2016 | On October 8, 2016, at approximately 1310 EDT, while in Mode 4 for a planned refueling outage, Shearon Harris Nuclear Power Plant experienced an undervoltage ( UV) condition in the switchyard for about 1.5 seconds. This triggered the UV relays for both emergency 6.9 kV buses and for several of the non-nuclear safety 6.9kV auxiliary buses, resulting in the respective supply breakers opening. At the time of the UV, the site was experiencing high winds and rain from the effects of Hurricane Matthew. Both Emergency Diesel Generators started and loaded as designed. Operations restored offsite power at 2154 EDT after verifying stable grid behavior for an extended period. Additionally, the Containment Ventilation Isolation system and the Auxiliary Feedwater system actuated and performed as designed.
The site declared an Unusual Event at 1328 EDT for loss of offsite power to emergency buses for greater than 15 minutes. At 2049 EDT, the Unusual Event was terminated.
The causes of the UV were determined to be a line fault on the Cape Fear - West End 230 kV line and equipment deficiencies associated with the Cape Fear 230 kV Substation protection relays which prevented immediate clearing of the fault. |
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Category:Letter
MONTHYEARML24290A1102024-10-24024 October 2024 Notification of Licensed Operator Initial Examination 05000400/2025301 05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-Out2024-10-23023 October 2024 Automatic Reactor Trip Due to Main Generator Lock-Out IR 05000400/20240112024-09-10010 September 2024 NRC Inspection Report 05000400/2024011 IR 05000400/20240052024-08-26026 August 2024 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400-2024005) Rev 1 ML24059A4252024-08-14014 August 2024 Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications ML24213A0522024-08-0202 August 2024 Issuance of Amendment No. 201 to Extend Completion Time of Inoperable Reactor Coolant System Accumulator Using Consolidated Line Item Improvement Process ML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000400/20240022024-07-29029 July 2024 – Integrated Inspection Report 05000400/2024002 ML24170A7312024-07-29029 July 2024 – Exemption from the Requirements of 10 CFR 50.55a(H)(2) Using the Risk-Informed Process for Evaluations Letter 05000400/LER-2024-001, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000400/20243022024-06-27027 June 2024 – NRC Operator Licensing Examination Approval 05000400/2024302 IR 05000400/20244012024-06-25025 June 2024 – Security Baseline Inspection Report05000400/2024401 ML24162A1372024-06-24024 June 2024 – Regulatory Audit Summary Related to the Review of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2)(EPID L-2024-LLE-00040) ML24136A1382024-05-20020 May 2024 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2024011) and Request for Information (RFI) ML24116A2592024-05-14014 May 2024 Staff Evaluation Related to Aging Management Plan and Inspection Plan for Reactor Vessel Internals ML24127A1592024-05-0808 May 2024 – Notification of Licensed Operator Initial Examination 05000400/2024302 IR 05000400/20240012024-05-0505 May 2024 Integrated Inspection Report 05000400/2024001 ML24100A0912024-04-10010 April 2024 Operator License Examination Report ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) IR 05000400/20230062024-02-28028 February 2024 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2023006 ML24032A2632024-02-23023 February 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0044 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter 05000400/LER-2022-006-02, Auxiliary Feedwater Pump Inoperability2023-07-11011 July 2023 Auxiliary Feedwater Pump Inoperability IR 05000400/20243012023-05-15015 May 2023 – Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 – Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 05000400/LER-1922-006-01, Auxiliary Feedwater Pump Inoperability2023-03-10010 March 2023 Auxiliary Feedwater Pump Inoperability IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 05000400/LER-2022-007-01, Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus2023-01-26026 January 2023 Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) 05000400/LER-2022-006, Auxiliary Feedwater Pump Inoperability2022-12-20020 December 2022 Auxiliary Feedwater Pump Inoperability 2024-09-10
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-Out2024-10-23023 October 2024 Automatic Reactor Trip Due to Main Generator Lock-Out 05000400/LER-2024-001, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out 05000400/LER-2022-006-02, Auxiliary Feedwater Pump Inoperability2023-07-11011 July 2023 Auxiliary Feedwater Pump Inoperability 05000400/LER-1922-006-01, Auxiliary Feedwater Pump Inoperability2023-03-10010 March 2023 Auxiliary Feedwater Pump Inoperability 05000400/LER-2022-007-01, Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus2023-01-26026 January 2023 Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus 05000400/LER-2022-006, Auxiliary Feedwater Pump Inoperability2022-12-20020 December 2022 Auxiliary Feedwater Pump Inoperability 05000400/LER-2022-007, Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus2022-12-20020 December 2022 Automatic Reactor Trip Due to Loss of Power from the ‘A’ Auxiliary Bus 05000400/LER-2022-008, Automatic Actuation of Auxiliary Feedwater System2022-12-19019 December 2022 Automatic Actuation of Auxiliary Feedwater System 05000400/LER-2022-005-01, Manual Reactor Trip Due to B Condensate Pump Motor Failure2022-11-28028 November 2022 Manual Reactor Trip Due to B Condensate Pump Motor Failure 05000400/LER-2022-005, Manual Reactor Trip Due to B Condensate Pump Motor Failure2022-10-21021 October 2022 Manual Reactor Trip Due to B Condensate Pump Motor Failure 05000400/LER-2022-004, Both Trains of High Head Safety Injection Inoperable2022-06-30030 June 2022 Both Trains of High Head Safety Injection Inoperable 05000400/LER-2022-003, Manual Reactor Trip Due to Degrading Condenser Vacuum2022-06-28028 June 2022 Manual Reactor Trip Due to Degrading Condenser Vacuum 05000400/LER-2022-001, Essential Services Chilled Water Chiller Inoperable Due to Pre-Rotation Vane Actuator Control Arm Position2022-03-10010 March 2022 Essential Services Chilled Water Chiller Inoperable Due to Pre-Rotation Vane Actuator Control Arm Position 05000400/LER-2016-0072017-02-0909 February 2017 Containment Spray System Valve Actuation, LER 16-007-01 for Shearon Harris Unit 1, Regarding Containment Spray System Valve Actuation 05000400/LER-2016-0062016-12-14014 December 2016 Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void, LER 16-006-00 For Shearon Harris Nuclear Plant, Unit 1 Regarding Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void 05000400/LER-2016-0042016-12-0707 December 2016 Reactor Trip and Safety Injection During Turbine Control Testing at Low Power, LER 16-004-00 for Shearon Harris, Unit 1, Regarding Reactor Trip and Safety Injection During Turbine Control Testing at Low Power 05000400/LER-2016-0052016-12-0707 December 2016 Offsite Power Undervoltage Caused Actuation of Several Systems, LER 16-005-00 for Shearon Harris Nuclear Power Plant, Unit 1 Regarding Offsite Power Undervoltage Caused Actuation of Several Systems 05000400/LER-2016-0022016-09-19019 September 2016 'A' Essential Services Chilled Water Chiller Trip due to Oil Leak from Failed Tube Fitting, LER 16-002-00 for Shearon Harris, Unit 1, Regarding 'A' Essential Services Chilled Water Chiller Trip Due to Oil Leak from Failed Tube Fitting 05000400/LER-2016-0012016-09-0101 September 2016 Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions, LER 16-001-00 for Shearon Harris, Unit 1, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions ML1015505742010-01-12012 January 2010 Event Notification for Harris on Offsite Notification Due to Discovery of Tritium in Water Leakage Onsite 2024-07-22
[Table view] |
comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Inf000llects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, 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- Shearon Harris Nuclear Power Plant - Unit 1 400 Energy Industry Identification System (EllS) and component codes are identified in the text as [XX].
A. Background
On October 8, 2016, Shearon Harris Nuclear Power Plant (HNP), was preparing for a planned refueling outage. At the time of the event, the unit was in Mode 4 and experiencing high winds and rain due to the effects of Hurricane Matthew.
HNP is connected to the transmission grid via a switchyard and 8 transmission lines. The transmission line initiating this event was the Cape Fear 230 kV line.
This event is reportable in accordance with 10 CFR 50.73(a)(2)(iv)(A), any event or condition that resulted in valid manual or automatic actuation of any of the following systems: reactor protection system, general containment isolation signals, emergency core cooling systems, auxiliary or emergency feedwater system, containment heat removal and depressurization systems, emergency AC electrical systems, emergency service water systems.
B. Event Description
On October 8, 2016, at approximately 1310 EDT, while in Mode 4 in preparation for a planned refueling outage, HNP experienced an undervoltage (UV) condition for approximately 1.5 seconds. The duration exceeded the UV relay time delay due to failure of transmission system relays to clear the faulted line within design parameters. This condition triggered the UV relays for both emergency 6.9 kV buses and for several of the non-safety related 6.9kV auxiliary buses, resulting in the respective supply breakers opening. The interruption in power caused the actuation of several safety systems.
Both Emergency Diesel Generators (EDGs) [EK] started and loaded as designed. The EDGs were allowed to run until 2154 EDT, after the grid had been declared stable by the Energy Control Center at 2033 EDT and grid performance had been verified by operations personnel. Additionally, the Containment Ventilation Isolation system [JM] and the Auxiliary Feedwater system [BA] actuated and performed as designed.
An Unusual Event was declared for the loss of offsite power to emergency buses for greater than 15 minutes.
C. Causal Factors Several causes were found to contribute to the UV condition. One cause was determined to be a line fault along the Cape Fear - West End 230kV line. A fallen tree was discovered near the location of the fault. Additionally, contact resistance was discovered at the protective relay within the Cape Fear 230 kV Substation which caused the delay in clearing the line fault. Further, a substation timing relay tripped at 88 cycles, which was beyond the 24 cycle design time. All causal factors, not within the authority of HNP, combined to decrease grid voltage to about 68% nominal, which is below the HNP UV relay setpoints.
comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Inf000llects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, 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- Shearon Harris Nuclear Power Plant, Unit 1 400
D. Corrective Actions
Completed: The Cape Fear — West End 230kV line was restored to its normal configuration on 10/8/2016. An additional feeder relay check was performed on 10/9/2016. The affected relays were calibrated or replaced as necessary.
Planned: An end-to-end test of the feeder/relay scheme is planned.
E. Safety Analysis
The safety significance of these events is low per Probabilistic Risk Assessment analysis. The station was in Mode 4 during a planned refueling outage. Station equipment operated as designed. Throughout the events, there were no significant adverse impacts to the health and safety of the public.
F. Additional Information
There is no prior operational experience at HNP involving the loss of offsite power to both emergency buses over the past three years.
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05000400/LER-2016-001 | Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions LER 16-001-00 for Shearon Harris, Unit 1, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000400/LER-2016-002 | 'A' Essential Services Chilled Water Chiller Trip due to Oil Leak from Failed Tube Fitting LER 16-002-00 for Shearon Harris, Unit 1, Regarding 'A' Essential Services Chilled Water Chiller Trip Due to Oil Leak from Failed Tube Fitting | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000400/LER-2016-003 | Containment High-Range Radiation Monitors Declared Inoperable Due to Potential for Temperature Induced Current | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000400/LER-2016-004 | Reactor Trip and Safety Injection During Turbine Control Testing at Low Power LER 16-004-00 for Shearon Harris, Unit 1, Regarding Reactor Trip and Safety Injection During Turbine Control Testing at Low Power | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000400/LER-2016-005 | Offsite Power Undervoltage Caused Actuation of Several Systems LER 16-005-00 for Shearon Harris Nuclear Power Plant, Unit 1 Regarding Offsite Power Undervoltage Caused Actuation of Several Systems | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000400/LER-2016-006 | Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void LER 16-006-00 For Shearon Harris Nuclear Plant, Unit 1 Regarding Reactor Vessel Closure Head Penetration Nozzle Indications Attributed to Primary Water Stress Corrosion Cracking and a Weld Fabrication Void | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000400/LER-2016-007 | Containment Spray System Valve Actuation LER 16-007-01 for Shearon Harris Unit 1, Regarding Containment Spray System Valve Actuation | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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