03-22-2016 | On January 26, 2016, at 2324 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.84282e-4 months <br />, the Control Room received a Steam Generator Steam Flow/Feed Flow mismatch alarm. Operators found Steam Generator ( SG) Train C Feedwater Regulating Valve closed and in manual. SG C Feedwater Regulating Valve could not be manually reopened. At 2325 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.846625e-4 months <br />, Operators manually tripped the Unit 1 reactor due to lowering level on SG C. The Auxiliary Feedwater ( AFW) system automatically actuated on a SG low level signal and operators took manual control of AFW at 2327 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.854235e-4 months <br />.
The cause of loss of Main Feedwater to SG C was a failure of the Manual 7300 Series Tracking Driver (NTD) circuit card which forced SG C Feedwater Regulating Valve-closed and prevented the operators from taking manual control or switching back to automatic valve control. As a corrective action, the Manual NTD circuit card was replaced. The manual actuation of the Reactor Protection System and subsequent automatic AFW actuation are both reportable under 10 CFR 50.73(a)(2)(iv)(A). The event was of very low risk significance and no radioactive release occurred; therefore, there was no adverse effect on the health and safety of the public. |
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LER-2016-001, Unit 1 Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed ClosedSouth Texas Unit 1 |
Event date: |
01-26-2016 |
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Report date: |
03-22-2016 |
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Reporting criterion: |
10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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4982016001R00 - NRC Website |
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Category:Letter
MONTHYEARML24029A2752024-01-29029 January 2024 Request to Reschedule Evaluated Force-on-Force Drill IR 05000498/20230042024-01-29029 January 2024 Integrated Inspection Report 05000498/2023004 and 05000499/2023004 ML24024A1162024-01-24024 January 2024 STP Unit 2 Request for Information IR 05000498/20244042024-01-18018 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000498/2024404; 05000499/2024404 IR 05000498/20230032023-12-28028 December 2023 Acknowledgment of Reply to a Notice of Violation (NRC Inspection Report 05000498/2023003 and 05000499/2023003) ML23360A1692023-12-26026 December 2023 FEMA, Submittal of Radiological Emergency Preparedness Final Report for the South Texas Project Medical Services Drill Evaluated on August 31, 2023 NOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 ML23326A2592023-12-0505 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23339A1902023-12-0505 December 2023 Update Foreign Ownership, Control, or Influence (FOCI) IR 05000498/20234012023-12-0404 December 2023 Security Baseline Inspection Report 05000498/2023401 and 05000499/2023401 ML23324A0102023-11-16016 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A2282023-11-13013 November 2023 Integrated Inspection Report 05000498/2023003 and 05000499/2023003, and Notice of Violation 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 ML23298A0002023-11-0101 November 2023 the Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 226 and 211 Related to Order Approving Indirect Transfer of Licenses and Conforming License Amendments ML23303A0782023-10-30030 October 2023 Submittal of Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments ML23279A0342023-10-30030 October 2023 Associated Independent Spent Fuel Storage Installation - Order Approving Indirect Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0004) (Letter) IR 05000498/20234032023-10-26026 October 2023 Material Control and Accounting Program Inspection Report 05000498/2023403 and 05000499/2023403 (Cover Letter) ML23317A1262023-10-12012 October 2023 South. Texas Project Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 26 ML23279A1382023-10-0505 October 2023 Responses to Requests for Additional Information Related to Application for Order Approving Indirect Transfer of Control of Licenses ML23271A1942023-10-0303 October 2023 Notification of Commercial Grade Dedication Inspection (05000498/2024013 and 05000499/2024013) and Request for Information ML23270B2592023-09-27027 September 2023 Update Foreign Ownership, Control, or Influence ML23263B1132023-09-20020 September 2023 Operator Licensing Examination Schedule Revision 1 IR 05000498/20243012023-09-0707 September 2023 Notification of NRC Initial Operator Licensing Examination 05000498/2024301; 05000499/2024301 IR 05000498/20233012023-09-0101 September 2023 NRC Examination Report 05000498/2023301 and 05000499/2023301 ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23236A6042023-08-24024 August 2023 Annual Dose Report for 2022 IR 05000498/20230052023-08-22022 August 2023 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023005 and 05000499/2023005) - Mid Cycle Letter ML23229A5262023-08-17017 August 2023 Inservice Inspection Summary Report - 1 RE24, ML23229A5892023-08-17017 August 2023 Voluntary Response to Regulatory Issue Summary (RIS) 2023-02, Scheduling Information for the Licensing of Accident Tolerant, Increased Enrichment, and Higher Burnup Fuels ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23228A2102023-08-15015 August 2023 Closure of Investigation (OI 4-22-19) ML23222A0322023-08-10010 August 2023 Report of Changes Made to Quality Assurance Program for Radioactive Material Packages ML23221A3002023-08-0909 August 2023 RE22 Inspection Summary Report for Steam Generator Tubinq, Rev. 1 (Epld L-2023-LRO-0029) ML23222A2792023-08-0909 August 2023 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) IR 05000498/20230022023-07-28028 July 2023 Integrated Inspection Report 05000498/2023002 and 05000499/2023002 ML23198A0532023-07-24024 July 2023 Request for Withholding Information from Public Disclosure ML23188A1612023-07-14014 July 2023 the Associated ISFSI - Notice of Consideration of Approval of Indirect Transfer of Licenses and Conforming Amendments and Opportunity to Request a Hearing (EPID L-2023-LLM-0004) - Letter ML23193A9932023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) ML23192A0482023-07-11011 July 2023 NRC Initial Operator Licensing Examination Approval 05000498/2023301; 05000499/2023301 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) ML23180A2822023-06-29029 June 2023 Operator Licensing Examination Schedule ML23177A2522023-06-26026 June 2023 Units 1, 2 & Independent Spent Fuel Storage Installation - Biennial Submittal of Technical Specification Bases Changes, Commitment Changes, 10 CFR 50.59 Evaluation Summary, and 10 CFR 72.48 Evaluation Summary ML23166B0802023-06-14014 June 2023 Update Foreign Ownership, Control, or Influence (FOCI) ML23163A1762023-06-12012 June 2023 Application for Order Approving Indirect Transfer of Control of Licenses 2024-01-29
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000498/LER-2017-0022018-01-22022 January 2018 Unit 1 Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil, LER 17-002-00 for South Texas Project, Unit 1, Regarding Condition Prohibited by Technical Specifications Due to Inoperable Control Room Envelope Makeup Filtration System Heating Coil 05000498/LER-2017-0012017-05-11011 May 2017 Unit 1 failure of a timing relay during a Technical Specification surveillance, LER 17-001-00 for South Texas, Unit 1, Regarding Failure of a Timing Relay During a Technical Specification Surveillance 05000498/LER-2016-0022016-06-29029 June 2016 Unit 1 Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip due to Generator Lockout, LER 16-002-00 for South Texas Project, Unit 1, Regarding Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip Due to Generator Lockout 05000498/LER-2016-0012016-03-22022 March 2016 Unit 1 Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed, LER 16-001-00 for South Texas Project, Unit 1, Regarding Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed NOC-AE-05001865, LER 05-01-00 South Texas Project Unit 2 Regarding Shutdown of STP Unit 2 Due to Reactor Coolant System Pressure Boundary Leak2005-04-0505 April 2005 LER 05-01-00 South Texas Project Unit 2 Regarding Shutdown of STP Unit 2 Due to Reactor Coolant System Pressure Boundary Leak NOC-AE-04001681, LER 01-03-007 for South Texas, Unit 1 Regarding Failure of Main Steam Power Operated Relief Valves 1B2004-02-18018 February 2004 LER 01-03-007 for South Texas, Unit 1 Regarding Failure of Main Steam Power Operated Relief Valves 1B NOC-AE-00000840, 1,Unauthorized Entry Into Protected Area,Safeguards Event Report2000-05-0404 May 2000 1,Unauthorized Entry Into Protected Area,Safeguards Event Report 2018-01-22
[Table view] |
Reported lessons leamed are incorporated into the licensing process and fed back to industry.
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I. Description of reportable event
A. Reportable event classification
This event is reportable under 10 CFR 50.73(a)(2)(iv)(A) as an event or condition that resulted in a manual actuation of the Reactor Protection System and also as an event or condition that resulted in an automatic actuation of the Auxiliary Feedwater (AFW) {BA} system.
B. Plant operating conditions prior to event
On January 26, 2016, Unit 1 was operating in Mode 1 at 100 percent power.
C. Status of structures, systems, and components (SSCs) that were inoperable at the start of the event and that contributed to the event There were no SSCs that were inoperable at the start of the event that contributed to the event.
D. Narrative summary of the event
On January 26, 2016, at 2324 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.84282e-4 months <br />, STP Unit 1 Control Room received a Steam Generator Steam FlOw/Feed Flow mismatch alarm. C Train Steam Generator (SG) Feedwater Regulating Valve {SJ} failed and could not be manually reopened.
At 2325 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.846625e-4 months <br />, Operators manually tripped the Unit 1 reactor due to lowering level in SG C which is reportable under 10 CFR 50.73(a)(2)(iv)(A) as a valid manual actuation of the Reactor Protection System.
At 2325 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.846625e-4 months <br />, all four AFW pumps actuated due to lowering SG C level. This event is reportable under 10 CFR 50.73(a)(2)(iv)(A) as a valid automatic actuation of the AFW system.
At 2327 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.854235e-4 months <br />, operators took manual control of AFW.
At 2333 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.877065e-4 months <br />, Operations tripped Steam Generator Feedwater Pumps 11, 12 and 13 and placed Startup Feedwater Pump in service.
At 2355, Main Feedwater was placed in service through the preheater bypass valves and Low Power Feedwater Regulating Valves to feed Steam Generators. The Auxiliary Feedwater Pumps were subsequently secured.
E. Method of discovery
The manual reactor trip and AFW actuation were self-revealing. A Steam Generator Flow/Feed Flow mismatch alarm was received. Operators found SG C Feedwater Regulating Valve closed and in manual. Operators attempted to open the valve both in manual and automatic without success. A manual reactor trip was initiated in response. The AFW system actuated automatically on a SG low level signal.
South Texas Unit 1 05000498
II. Component failures
A. Failure mode, mechanism, and effects of failed component
The component failure applicable to this Licensee Event Report (LER) is related to the Manual 7300 Series Tracking Driver (NTD) circuit card {JB} which controls the SG C Feedwater Regulating Valve.
The cause of the Manual NTD circuit card failure was due to an integrated circuit (IC) chip (W30-2) output pin 8 which failed low. This chip is in the PRIORITY LOWER circuit and with the failed condition it forced the circuit card into the manual mode and drove the output to 0%.
This caused the Manual/Auto (M/A) station to shift to the manual mode and is the reason Operators could not get the Feedwater Regulating Valve to respond when depressing the RAISE button on the M/A station. This condition caused the SG C Feedwater Regulating Valve to close, lowering SG C level, and resulting in Operators manually tripping the reactor.
B. Cause of component failure
The cause of the NTD circuit card failure was attributed to random failure of an electronic component.
C. Systems or secondary functions that were affected by failure of components with multiple functions The SG C Feedwater Regulating Valve does not have multiple functions that affect other systems. The failure of this component contributed to the manual reactor trip.
D. Failed component information (Energy Industry Identification System (EIIS) designators provided in {brackets}) Main Feedwater System {SJ} Feedwater/ Steam Generator Water Level Control System {JB} 7300 Series Tracking Driver NTD card {CBD} Manufacturer: Westinghouse Electric Corporation {W120} Model: 2838A45G01
III. Analysis of the event
A. Safety system responses that occurred
The Reactor Protection System and AFW systems both responded to this event.
B. Duration of safety system inoperability
There were no SSCs that were inoperable at the start of the event that contributed to the event.
C. Safety consequences and implications
No Technical Specification LCOs were entered due to this event. Operators manually tripped the reactor following the loss of Main Feedwater to SG C.
For the Probabilistic Risk Assessment (PRA) analysis, the initiating event is classified as a Partial Loss of Main Feedwater (PLMFW) — the isolation of main feedwater to SG C led to decreasing levels in the SG C which resulted in a reactor trip. The PLMFW event is a modeled initiating event, and no risk significant equipment was confirmed out of service.
The STP PRA was used to estimate the relevant metrics for a reactor trip, Conditional Core Damage Probability (CCDP) and Conditional Large Early Release Probability (CLERP), given that the PLMFW initiating event actually occurred. The CCDP and CLERP were determined to be 6.1E-07 and 3.6E-08 respectively, indicating very low risk significance.
The event was of very low risk significance and no radioactive release occurred; therefore, there was no adverse effect on the health and safety of the public.
IV. Cause of the event
Prior to the manual reactor trip, SG C Feedwater Regulating Valve closed resulting in lowering water level in SG C due to the random failure of the Manual 7300 Series Tracking Driver circuit card. The Manual NTD card failure forced the Feedwater Regulating Valve closed and prevented further operation of the valve. Operators initiated a manual reactor trip due to lowering SG level and the AFW system actuated automatically on a SG low level signal. There were no human performance errors that contributed to the event.
V. Corrective actions
The Manual NTD circuit card was replaced. The circuit card was installed in 2009. The failure of the card is considered an infant mortality failure (i.e.
first documented failure for this type. The Preventive Maintenance replacement frequency for these NTD circuit cards is 15 years.
A review of all Auto and Manual NTD circuit cards installed in the Feedwater Regulating Valve loops in Unit 1 and Unit 2 indicate they were installed 8 to 11 years ago and all have different sequenced serial numbers which indicates they are not manufactured from the same lot.
VI. Previous similar events
An Operating Experience review was conducted as part of the cause evaluation performed for this event.
Five other NTD card failures occurred while in service since 1998. All but one failure caused a minor plant transient requiring operator action. In 2001, a modification was made to the Feedwater Regulating Valve loops to add dual NTD cards (auto and manual) to increase reliability of this single point vulnerability circuit. In 2004, the loop was modified again to add computer points to monitor the 0-10 VDC output signal of both the Auto and Manual NTD cards which provides an annunciation to alert the Control Room Operators of degraded/failed conditions. The last failure occurred in 2009 in Unit 2 after both modifications were installed.
The card failure did not cause a plant transient because the Control Room received an alarm identifying the degraded condition. The 2009 failure occurred after the Manual NTD card was in service for approximately 1 year.
There were no previous STP Licensee Event Reports submitted related to failure of dual tracker (auto and manual) NTD card.
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05000498/LER-2016-001 | Unit 1 Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed LER 16-001-00 for South Texas Project, Unit 1, Regarding Manual Reactor Trip due to Loss of Main Feedwater to C Train Steam Generator When the Steam Generator Feedwater Regulating Valve Failed Closed | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000498/LER-2016-002 | Unit 1 Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip due to Generator Lockout LER 16-002-00 for South Texas Project, Unit 1, Regarding Automatic Reactor Trip and Auxiliary Feedwater System Actuation Following Turbine Trip Due to Generator Lockout | 10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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