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Category:Letter
MONTHYEARIR 05000498/20244022024-10-23023 October 2024 Security Baseline Inspection Report 05000498/2024402 and 05000499/2024402 05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function ML24295A0772024-10-21021 October 2024 Licensed Operator Positive Fitness-for-Duty Test 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function NOC-AE-240040, Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2024-10-16016 October 2024 Change to South Texas Project Electric Generating Station (STPEGS) Emergency Plan IR 05000498/20243012024-10-0707 October 2024 NRC Examination Report 05000498/2024301 and 05000499/2024301 ML24255A0322024-09-30030 September 2024 The Associated Independent Spent Fuel Storage Installation - Notice of Consideration of Approval of Direct Transfer of Licenses and Opportunity to Request a Hearing (EPID L-2024-LLM-0002) - Letter ML24269A1762024-09-25025 September 2024 Tpdes Permit Renewal Application WQ0001 908000 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps ML24271A3022024-09-18018 September 2024 STP-2024-09 Post-Exam Comments - Redacted ML24274A0902024-09-16016 September 2024 Written Response - EA-24-026 STP Operator - Redacted ML24250A1882024-09-11011 September 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal ML24249A3372024-09-0404 September 2024 Inservice Inspection Summary Report - 2RE23 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators ML24234A0912024-08-27027 August 2024 NRC Initial Operator Licensing Examination Approval 05000498/2024301; 05000499/2024301 IR 05000498/20240052024-08-22022 August 2024 Updated Inspection Plan for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2024005 and 05000499/2024005) IR 05000498/20240022024-08-0909 August 2024 Integrated Inspection Report 05000498/2024002 and 05000499/2024002 IR 05000498/20240102024-08-0808 August 2024 Biennial Problem Identification and Resolution Inspection Report 05000498/2024010 and 05000499/2024010 ML24213A0842024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses ML24218A1462024-07-26026 July 2024 2. EPA Comments on South Texas Project Exemption Ea/Fonsi ML24207A1782024-07-25025 July 2024 Licensed Operator Positive Fitness-For-Duty Test 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function IR 05000498/20244042024-06-0303 June 2024 Cyber Security Inspection Report 05000498/2024404 (Cover Letter) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2872024-05-15015 May 2024 Submittal of 2024 Nrc/Fema Evaluated Exercise Scenario Manual ML24136A2842024-05-15015 May 2024 Independent Spent Fuel Storage Installation Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance ML24137A0882024-05-15015 May 2024 Operator Licensinq Examination Schedule Revision 3 ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24128A1572024-05-0707 May 2024 Independent Spent Fuel Storage Installation Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000498/20240012024-05-0606 May 2024 Integrated Inspection Report 05000498/2024001 & 05000499/2024001 ML24120A3762024-04-29029 April 2024 Annual Dose Report for 2023 ML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24116A3032024-04-25025 April 2024 Operations Quality Assurance Plan Condition Adverse to Quality Definition Change Resulting in a Reduction in Commitment ML24117A1602024-04-24024 April 2024 2023 Radioactive Effluent Release Report ML24102A2452024-04-23023 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0046 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24113A3122024-04-22022 April 2024 Cycle 24 Core Operating Limits Report ML24097A0072024-04-0606 April 2024 Relief Request Number RR-ENG-4-07 – Request for an Alternative to ASME Code Case N-729-6 for Reactor Vessel Head Penetration 75 ML24092A1902024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24088A3022024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update ML24081A3972024-03-21021 March 2024 Response to Request for Additional Information for Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24080A2902024-03-19019 March 2024 Nuclear Liability Certificates of Insurance ML24066A2002024-03-0606 March 2024 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes ML24079A1312024-03-0505 March 2024 Nuclear Insurance Protection ML24060A1742024-02-28028 February 2024 Submittal of Annual Fitness for Duty Performance Report for 2023 IR 05000498/20230062024-02-28028 February 2024 Annual Assessment Letter for South Texas Project Electric Generating Station, Units 1 and 2 (Report 05000498/2023006 and 05000499/2023006) IR 05000498/20240132024-02-27027 February 2024 Design Basis Assurance Inspection (Programs) Commercial Grade Dedication IR 05000498/2024013 and 05000499/2024013 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000499/LER-2024-003, Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function2024-10-22022 October 2024 Containment Isolation Valve Inoperable Resulting in Condition Prohibited by Technical Specification and Prevention of Fulfillment of Safety Function 05000499/LER-2024-002, Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-10-17017 October 2024 Two Control Room Envelope HVAC Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2024-004, Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps2024-09-19019 September 2024 Loss of Offsite Power Resulting in Unit 1 Automatic Reactor Trip and Actuation of Emergency Diesel Generators and Auxiliary Feedwater Pumps 05000499/LER-2024-001-01, Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-08-29029 August 2024 Supplement to Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000499/LER-2024-001, Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators2024-07-0202 July 2024 Automatic Reactor Trip and Actuation of Two of Three Emergency Diesel Generators 05000498/LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump2024-07-0101 July 2024 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump 05000498/LER-2024-002-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-27027 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-003-01, Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function2024-06-19019 June 2024 Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function ML24130A2712024-05-0909 May 2024 Re Two Essential Chilled Water Trains Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/LER-2023-004-01, Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water2024-04-25025 April 2024 Condition Prohibited by Technical Specifications Due to Inoperable Train of Essential Chilled Water ML24092A1902024-04-0101 April 2024 Re Two Steam Generator Power Operated Relief Valves (Porvs) Inoperable Resulting in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000498/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 2024-09-19
[Table view] |
LER-2024-003, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump |
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July 1, 2024 NOC-AE-24004046 10 CFR 50.73 STI: 35608947 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 South Texas Project Unit 1 Docket No. STN 50-498 Licensee Event Report 2024-003-00 Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump
Pursuant to reporting requirements in 10 CFR 50.73(a)(2)(i)(B) and 10 CFR 50.73(a)(2)(v)(D),
STP Nuclear Operating Company (STPNOC) hereby submits the attached South Texas Project Unit 1 Licensee Event Report 2024-003-00 for a condition prohibited by Technical Specifications and for an event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.
The event did not have an adverse effect on the health and safety of the public.
There are no commitments in this submittal.
If there are any questions regarding this submittal, please contact Chris Warren at (361) 972-7293 or me at (361) 972-4778.
Kimberly A. Harshaw Executive Vice President and Chief Nuclear Officer
Enclosure: Unit 1 LER 2024-003-00, Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump
cc:
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 E. Lamar Boulevard Arlington, TX 76011-4511 NOC-AE-24004046 Enclosure
ENCLOSURE
Unit 1 LER 2024-003-00
Condition Prohibited by Technical Specifications and Potential Loss of Safety Function Due to Inoperable Low Head Safety Injection Pump
1. Description of the Reportable Event
A. Reportable Event Classification
This event is reportable pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by Technical Specifications (TS) and 10 CFR 50.73(a)(2)(v)(D) as a condition that could have prevented fulfillment of a safety function.
TS 3.5.2 action statement "a" for an INOPERABLE Low Head Safety Injection (LHSI) pump allows continued operation for up to either 7 days if at least two High Head Safety Injection (HHSI) pumps, two LHSI pumps, associated Residual Heat Removal (RHR) heat exchangers, and required flow paths from the Refueling Water Storage Tank to the Reactor Coolant System (RCS) are OPERABLE. The LHSI pump must be returned to OPERABLE status after 7 days or apply the requirements of the Configuration Risk Management Program (CRMP). If neither action (i.e. pump restoration to OPERABLE or application of CRMP requirements) is completed, then the Unit must be in HOT STANDBY (Mode 3) within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN (Mode 4) withing the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
TS 3.5.2 action statement "b" for less than two of the required Emergency Core Cooling System (ECCS) subsystems OPERABLE requires restoration of at least two ECCS subsystems to OPERABLE status within one hour or apply the requirements of CRMP. If neither action is completed, then the Unit must be in HOT STANDBY (Mode 3) within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN (Mode 4) withing the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
In this event, the Unit operated from April 3, 2023 until April 21, 2024 with LHSI pump 1A INOPERABLE without entering TS 3.5.2 action statement "a" and TS 3.5.2 action statement "b" when a second train of ECCS was INOPERABLE for maintenance or surveillance testing. This exceeds the 7-day restoration time in action statement "a" and the 1-hour restoration time in action statement "b". The requirements of CRMP were not applied for either action statement.
The analyzed accidents in the STP Updated Final Safety Analysis Report (UFSAR) that rely on ECCS for reactor core cooling and criticality control assume one train of ECCS is unavailable during the accidents. During a design basis Loss of Cooling Accident (LOCA), one unaffected (i.e. OPERABLE) ECCS train delivers make-up water to the affected RCS train with the pipe break while the second unaffected ECCS train provides additional cooling capabilities to reactor core. There were several instances from April 3, 2023 until April 21, 2024 where less than the required number of ECCS trains were OPERABLE to mitigate the consequences of an accident.
B. Plant Operating Conditions Prior to Event
Prior to the event, Unit 1 was in Mode 1 at 100% power.
C. Status of Structures, Systems, and Components That Were Inoperable at the Start of the Event and That Contributed to the Event
At the time of discovery, there were no other structures, systems, or components that were INOPERABLE that contributed to the event.
D. Narrative Summary of the Event
Timeline (Note: All times listed are Central Daylight Time)
03/23/2023 (1404): Train 'A' ECCS (includes LHSI pump 1A) declared INOPERABLE for the 'A' Train work window during the Unit 1 refueling outage.
04/02/2023: LHSI Pump 1A did not start. Breaker was re-racked and pump successfully started on the next attempt.
04/03/2023: Hand switch for LHSI Pump 1A was replaced. During the Post Maintenance Test (PMT), the first attempt to start the pump was unsuccessful. Electrical maintenance observed the breaker (did not perform any manipulations) when a 2nd attempt to start the pump was successful. The breaker was not cycled between pump start attempts.
04/03/2023 (1131): Train 'A' work window for Unit 1 refueling outage closed. LHSI pump 1A remains INOPERABLE and is a restraint to entering Mode 4 (Hot Standby).
04/04/2023: Replacement breaker for LHSI Pump 1A was installed with successful PMT. The breaker installed has the unrestrained washer.
04/04/2023 (2317): Operations declared LHSI pump 1A OPERABLE.
04/21/2024: During performance of Residual Heat Removal System Valve Operability Test, LHSI PUMP 1A failed to start.
When hand switch was placed in the START position the green light momentarily flickered off and the red light never illuminated. The Train A LHSI, High Head Safety Injection (HHSI), Containment Spray System (CSS) pump cubicle and containment sump isolation valve cubicle cooler fans did not start. A brief thump was heard from the motor but no shaft rotation was observed. No protective devices appear to be actuated on SWGR E1A Cubicle 6.
04/22/2024: Electrical maintenance started performing breaker inspections and troubleshooting.
04/23/2024: Electrical maintenance continued troubleshooting activities. A loose wire for the hand switch red light tightened and the red bulb was replaced.
04/24/2024: Electrical maintenance identified the unrestrained washer on a support plate above the "A" phase vacuum interrupter. A picture is provided in the Attachment. The breaker was removed and a spare breaker was installed with a successful PMT.
04/25/2024 (0341): Operations declared LHSI pump 1A OPERABLE.
E. Method of Discovery
The event was self-revealing when the LHSI pump 1A would not start on April 21, 2024. The unrestrained washer was identified in the breaker on April 24, 2024. The vendor provided confirmation the washer was present when the breaker was shipped to STP.
II. Component Failures
A. Failure Mode, Mechanism, and Effects of the Failed Components
The failed component in this event was the Train 'A' LHSI pump 1A breaker due to an unrestrained washer, which was foreign material, in the breaker. The presence of the washer adversely impacted the seismic qualification of the breaker, though the washer did not physically affect the functionality of the breaker until one year following installation. Based on a fault tree performed by Engineering, the most likely cause of the breaker's failure to close was due to either mechanical binding or a failure of the breaker's closed position latch, both of which could have been caused by the presence of the unrestrained washer. The circuit to energize LHSI pump 1A was not completed due to the washer preventing the breaker from fully closing.
B. Cause of Component Failure
Based on a fault tree performed by Engineering, the most likely cause of the breaker's failure to close was due to either mechanical binding or a failure of the breaker's closed position latch, both of which could have been caused by the presence of the unrestrained washer. Engineering was able to refute any contact, relay, charging springs, motor, and manufacturing flaws that could have caused the breaker to not perform its design functions.
C. Systems or Secondary Functions That Were Affected by Failure of Components with Multiple Functions
Train 'A' Emergency Core Cooling System was INOPERABLE due to the inoperability of LHSI pump 1A.
D. Failed Component Information
System: Residual Heat Removal/Low Pressure Safety Injection System { BP }
Component: Breaker { BKR }
Manufacturer: Siemens { S125 }
Model: { 5HKR-250-1200-58 }
III. Analysis of Event
A. Safety System Responses that Occurred
No safety system responses occurred because of this event.
B. Duration of Safety System Inoperability
LHSI Pump 1A was INOPERABLE from 2317 on April 4, 2023, until 0341 on April 25, 2024, when LHSI Pump 1A was declared OPERABLE. This was a total 386 days and 24 minutes.
C. Safety Consequences and Implications
The increase in risk due to the inoperability of LHSI Pump 1A for the condition identified represents a very small change in risk. This assessment considered LHSI Train A unavailable during a seismic initiating event for 04/03/23 to 04/02/24, the time the breaker with the foreign material was installed until the last successful start of the LHSI Pump 1A, and the unavailability for LHSI Train A for all initiators for 04/02/24 to 04/25/24, the time of the last successful LHSI Pump 1A start until the pump was declared operable following corrective maintenance. This resulted in a total Incremental Core Damage Probability of 2.1872E-07 and a total Incremental Large Early Release Probability of 2.5568E-11. These results are within Region III for very small changes in risk per Regulatory Guide 1.174.
IV. Cause of the Event
The cause of the event was determined to be an error by the vendor when the washer was introduced into the breaker prior to shipping to STP. The purchase order for the component did have a requirement for the vendor to provide components free of foreign material. STP procurement and quality control personnel performed procedurally-required foreign material inspections during receipt activities and did not see the foreign material. STP Electrical Maintenance personnel performed another foreign material inspection prior to installation and did not see the foreign material.
V. Corrective Actions
Completed:
- 1. Condition Report (CR) Action 24-4015-8: Perform Extent of Condition review on all 4.16kV safety related breakers procured under Purchase Order 264203.
Planned:
- 1. CR Action 24-4015-18: Perform a foreign material inspection of breaker A2PKSG0E1A9, Serial Number
- R-3009529574A-002.
- 2. CR Action 24-4015-19: Perform a foreign material inspection of breaker A2PKSG0E1A10, Serial Number
- R-3009529574A-001.
VI. Previous Similar Events
No previous similar events that could have precluded this event were identified.
Attachment:
Picture of LHSI Pump 1A Breaker with As-Found Unrestrained Washer Attachment Picture of LHSI Pump 1A Breaker with As-Found Unrestrained Washer