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05-31-2016 | On April 1, 2016 the 345/13.8kV high voltage station auxiliary transformer ( 1X-03) tripped on a differential current relay (1-87A/X-03) actuation. Review of this event determined that there were three instances over the past three years when the required action completion time for not satisfying the Limiting Conditions For Operation of Technical Specification 3.8.1 ( AC Sources - Operating) and 3.8.2 ( AC Sources - Shutdown) would have been exceeded with the latent error present.
This event is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B) for operation or condition prohibited by technical specifications. |
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Category:Letter
MONTHYEARML24295A0862024-10-21021 October 2024 Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002 L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024 LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - 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[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000266/LER-2017-0032017-12-13013 December 2017 Degraded Condition, LER 17-003-00 for Point Beach Nuclear Plant, Unit 1, Regarding Degraded Condition 05000266/LER-2017-0022017-12-13013 December 2017 Operation or Condition Prohibited by Technica Specifications, LER 17-002-00 for Point Beach Nuclear Plant, Unit 1, Regarding Operation or Condition Prohibited by Technical Specifications 05000266/LER-2017-0012017-11-16016 November 2017 Control Room Barrier Inadvertently Disabled, LER 17-001-00 for Point Beach, Unit 1, Regarding Control Room Barrier Inadvertently Disabled 05000266/LER-2016-0032016-06-0101 June 2016 Operation or Condition Prohibited by Technical Specifications, LER 16-003-00 for Point Beach, Unit 1, Regarding Operation or Condition Prohibited by Technical Specifications 05000266/LER-2016-0022016-05-31031 May 2016 Operation or Condition Prohibited by Technical Specifications, LER 16-002-00 for Point Beach, Unit 1, Regarding Operation or Condition Prohibited by Technical Specifications 05000266/LER-2016-0012016-05-12012 May 2016 Unit 1 Degraded Condition, LER 16-001-00 for Point Beach, Unit 1, Regarding Degraded Condition 2017-12-13
[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 Internet e-mail to 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.
Description of the Event:
At 1132 On April 1, 2016 the 345/13.8kV high voltage station auxiliary transformer (1X-03) tripped on a differential current relay (1-87A/X-03) actuation. Review of this event determined that there were three instances over the past three years when the required action completion time for not satisfying the Limiting Conditions For Operation of Technical Specification 3.8.1 (AC Sources — Operating) and 3.8.2 (AC Sources — Shutdown) would have been exceeded with the latent error present.
This 60 day licensee event report is being submitted in accordance with the requirements of 10 CFR 50.73(a)(2)(i)(B).
Cause of the Event:
The cause of the operation or condition prohibited by technical specifications has been determined to be a wiring error introduced on April 3, 2013.
Analysis of the Event:
The 345/13.8kV high voltage station auxiliary transformer (1X-03) tripped on a differential current relay (1-87A/X-03) actuation while starting a Reactor Coolant Pump motor. The actuation triggered a 1X-03 lockout. During the event, an automatic fast bus transfer occurred as designed powering the 13.8kV/4.16kV low voltage station auxiliary transformer (1X-04) from offsite power through the opposite unit 345/13.8kV high voltage station auxiliary transformer (2X-03). An under voltage condition was not detected on the downstream 4.16kV safeguard bus switchgear (1A-05 or 1A-06) that would have started the emergency diesel generators. Operations promptly restored equipment affected by the 1X-03 lock out, including station battery chargers (D-07 and D-108) within four minutes. The 1X-04 transformer was returned to service through the 1X-03 transformer at 2342 on April 1, 2016.
An event investigation team determined the cause of the event to be a wiring error associated with the differential current relay. With the wiring error present, actuation of the relay was dependent upon the loading of the transformer.
As transformer load would increase, the relay would get closer to its actuation. If the relay actuated, the 1X-03 transformer would lock out and remove the circuit from the offsite transmission network. This is what occurred during the April 1, 2016 event.
Technical Specification 3.8.1 requires the associated unit X-03 transformer to be operable. Technical Specification 3.8.2 requires an offsite circuit to be operable. Analysis of the 1X-03 transformer load data for the past three years determined there were three instances when the required action completion time for not satisfying the Limiting Conditions For Operation of Technical Specification 3.8.1 and 3.8.2 would have been exceeded.
Safety Significance:
The condition was determined to be of very low safety significance. If the condition would have presented itself, Operations would have promptly restored equipment affected by the 1X-03 lock out. If an under voltage condition would have been detected on the downstream 1A-05 or 1A-06, the emergency diesel generators would have started and powered safety systems, structures or components needed to shut down the reactor, maintain safe shutdown conditions, remove residual heat, control the release of radioactive material or mitigate the consequences of an accident. There was no impact on the health and safety of the public as a result of this condition.
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 internet e-mail to 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.
3. LER NUMBER
2016 002 - 00
Corrective Actions:
The 1X-03 transformer differential current relay wiring error has been corrected. A corrective action has been created from the extent of condition review of work performed by contractors to enhance the contractor training on the proper use of plant processes for lifting and landing wires/leads on equipment.
Similar Events:
There have not been similar events of this condition prohibited by technical specifications reported in the past three years.
Component Failure Data:
None