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Category:Letter
MONTHYEARIR 05000400/20240032024-11-0707 November 2024 Integrated Inspection Report 05000400/2024003 ML24290A1102024-10-24024 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 05000400/LER-1922-006-01, Auxiliary Feedwater Pump Inoperability2023-03-10010 March 2023 Auxiliary Feedwater Pump Inoperability ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 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-2021-005, Past Inoperability of Effluent Accident Monitor Exceeded Time Allowed by Technical Specifications2021-08-23023 August 2021 Past Inoperability of Effluent Accident Monitor Exceeded Time Allowed by Technical Specifications 05000400/LER-2021-004, Pressurizer Safety Valve Lift Setpoint Drifted Outside of Technical Specification Tolerance2021-06-21021 June 2021 Pressurizer Safety Valve Lift Setpoint Drifted Outside of Technical Specification Tolerance 05000400/LER-2021-002-01, Re All ECCS Accumulator Isolation Valves Closed in Mode 3 with RCS Pressure Greater than 1000 Psig2021-03-15015 March 2021 Re All ECCS Accumulator Isolation Valves Closed in Mode 3 with RCS Pressure Greater than 1000 Psig 05000400/LER-2021-001, Automatic Reactor Trip Due to Faults on Non-Segregated Bus from Unit Auxiliary Transformer 1B2021-02-16016 February 2021 Automatic Reactor Trip Due to Faults on Non-Segregated Bus from Unit Auxiliary Transformer 1B 05000400/LER-2021-002, All ECCS Accumulator Isolation Valves Closed in Mode 3 with RCS Pressure Greater than 1000 Psig2021-02-15015 February 2021 All ECCS Accumulator Isolation Valves Closed in Mode 3 with RCS Pressure Greater than 1000 Psig 05000400/LER-2020-002, Re Manual Reactor Trip Due to Control Rod Drop During Surveillance Testing2020-10-12012 October 2020 Re Manual Reactor Trip Due to Control Rod Drop During Surveillance Testing 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
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(_~ DUKE ENERGY David S. Hoffman Plant Manager Shearon Harris Nuclear Power Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 10 CFR 50.73 October 23, 2024 Serial: RA-24-0261 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63 Subject: Licensee Event Report 2024-001-01 Ladies and Gentlemen:
Duke Energy Progress, LLC, submits the enclosed Licensee Event Report 2024-001-01 in accordance with 10 CFR 50.73(a)(2)(iv)(A) for Shearon Harris Nuclear Power Plant, Unit 1 (HNP). This event had no significance with respect to the health and safety of the public.
This report is a planned supplement to LER 2024-001-00 submitted on July 22, 2024.
There are no regulatory commitments contained within this report.
Please refer any questions regarding this submittal to Mike Hershkowitz at (984) 229-2828.
Sincerely, ~
7/4--
David S. Hoffman Enclosure: Licensee Event Report 2024-001 -01 cc:
D. Jung, NRC Senior Resident Inspector, HNP N. Jordan, NRC Project Manager, HNP NRC Regional Administrator, Region II
Abstract
Shearon Harris Nuclear Power Plant, Unit 1
00400 3
Automatic Reactor Trip Due to Main Generator Lock-Out 05 30 2024 2024 001 01 10 23 2024 1
100
Mike Hershkowitz, Regulatory Affairs (984) 229-2828 B
EA NSBU H200 Y
B EA NSBU H200 Y
On May 30, 2024, at 19:49 Eastern Daylight Time, Shearon Harris Nuclear Power Plant, Unit 1, experienced an automatic reactor trip from 100 percent power due to lock-out of the main generator caused by an electrical fault in the non-segmented bus at the 6.9 kV bushing box of Unit Auxiliary Transformer (UAT) 1B. UAT-1B was replaced during the 2024 spring refueling outage. Following the reactor trip, the unit was stabilized in Mode 3 at normal operating temperature and pressure. The reactor trip was not complex, with all systems responding normally post-trip. Local observation identified damage to the UAT-1B Y-side non-segregated bus at the connection to the low side bushing box. The reactor trip was reported on May 30, 2024, under 10 CFR 50.72(b)(2)(iv)(B) as an event or condition that results in actuation of the reactor protection system when the reactor is critical. The event had no impact on the health and safety of the public. A root cause evaluation determined site personnel did not adequately evaluate the design of the Daburn 2476/10 cable for use as a potential transformer (PT) sensing cable. The root cause evaluation identified a similar cause and condition was present on the Startup Transformer (SUT) 1A that resulted in a condition prohibited by Technical Specifications. To correct these conditions, the engineering design of UAT-1B and SUT-1A was changed and the PT sensing cable was removed.Page of
- 3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.
052 050 A train of offsite power being declared inoperable and TS 3.8.1.1.a LCO action entry. Local observation identified the nonsegregated bus between the SUT-1A and east side of the Turbine Building was damaged.
C. Causal Factors The UAT-1B and SUT-1A non-segmented bus failures were caused by an electrical fault on the potential transformer (PT) cables associated with the load tap changers. The applied voltage on the PT cables was nominal 4 kilovolts AC, phase to ground, and Daburn 2476/10 cables were used for these applications. Daburn 2476/10 cables use a fluorinated ethylene propylene (FEP) insulation and are rated for 50 kilovolts DC. There is no published AC rating for Daburn 2476/10 cables.
Testing subsequently revealed that new cables fail at 4 kV AC given enough time. The root cause of the UAT-1B and SUT-1A non-segmented bus failures was that site personnel did not adequately evaluate the design of the Daburn 2476/10 cable for use as a PT sensing cable in accordance with procedural guidance.
D. Corrective Actions UAT-1B has been isolated from the onsite electrical system. HNP was synchronized to the grid at 13:26 on June 1, 2024.
Power is aligned to train 'B' electrical loads through SUT-1B. SUT-1A was returned to service to restore A train offsite power operability on May 22, 2024.
To correct the condition, the engineering design of UAT-1B and SUT-1A was changed and the PT sensing cable was removed. To correct the cause, the site will implement a design change for the on-load tap changer voltage sensing cable.
Engineering change refresher training will be provided to qualified personnel at HNP on the selection and evaluation of design inputs.
E. Safety Analysis Following the reactor trip and loss of power from UAT-1B, the power supply was automatically fast transferred from UAT-1B to SUT-1B, maintaining the power supply to the associated safety bus. Loads from UAT-1A were also fast transferred to SUT-1A, in accordance with plant design. The automatic reactor trip was not complex, with all safety systems functioning as designed during and following the reactor trip. This reactor trip had no impact on the health and safety of the public. During the timeframe that the A train of offsite power was inoperable in Modes 1, 2, 3, and 4 on May 4, 2024, through May 22, 2024, the B train of the offsite power system remained operable to fulfill the safety function of providing AC power to HNP. Based upon the availability of the B train of offsite power and the EDGs during this timeframe, this event is not considered to be safety significant.
F. Additional Information There have been no events at HNP similar to the event documented in this LER in the past three years.
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Shearon Harris Nuclear Power Plant, Unit 1 00400 2024 001 01