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Category:Letter
MONTHYEARNL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) ML24120A2832024-04-30030 April 2024 Project Manager Reassignment 2024-09-09
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal 05200025/LER-2024-001, Condition Prohibited by Technical Specification Limiting Condition of Operation 3.1.6 Control Bank Overlap Limits Exceeded Due to Inadequate Procedure Guidance2024-03-18018 March 2024 Condition Prohibited by Technical Specification Limiting Condition of Operation 3.1.6 Control Bank Overlap Limits Exceeded Due to Inadequate Procedure Guidance ND-24-0046, (Vegp), Unit 3, Condition Prohibited by Technical Specification Limiting Condition of Operation 3.1.6 Control Bank Overlap Limits Exceeded Due to Inadequate Procedure Guidance2024-03-18018 March 2024 (Vegp), Unit 3, Condition Prohibited by Technical Specification Limiting Condition of Operation 3.1.6 Control Bank Overlap Limits Exceeded Due to Inadequate Procedure Guidance 05000424/LER-2023-002, Manual Reactor Trip Due to Failure of a Heater Drain Pump and Standby Condensate Pump2023-10-11011 October 2023 Manual Reactor Trip Due to Failure of a Heater Drain Pump and Standby Condensate Pump 05200025/LER-2023-006, Regarding Automatic Reactor Protection System Actuation During Startup Testing Due to Auto Reactive Power Regulator Being Active While in Island Mode Operation2023-09-19019 September 2023 Regarding Automatic Reactor Protection System Actuation During Startup Testing Due to Auto Reactive Power Regulator Being Active While in Island Mode Operation 05200025/LER-2023-005, Automatic Reactor Protection System Actuation During Startup Testing Due to Inadequate Turbine Trip Logic2023-09-0606 September 2023 Automatic Reactor Protection System Actuation During Startup Testing Due to Inadequate Turbine Trip Logic ND-23-0439, ITAAC Closure Notification on Completion of ITAAC 2.2.05.07a.i (Index Number 265)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.05.07a.i (Index Number 265) 05200025/LER-2023-004, Manual Reactor Protection System Actuation Due to Condenser Flanges Not Removed During Construction2023-06-30030 June 2023 Manual Reactor Protection System Actuation Due to Condenser Flanges Not Removed During Construction 05200025/LER-2023-003, Automatic Reactor Protection System Actuation During Startup Testing Due to Incorrect Turbine Control Valve Setting2023-06-0808 June 2023 Automatic Reactor Protection System Actuation During Startup Testing Due to Incorrect Turbine Control Valve Setting 05200025/LER-2023-002, Automatic RPS Actuation Durin9 Mode 1 Due to Incorrect Relay Settings Caused by Less than Adequate Questioning Attitude, Validation of Assumptions, and Interface/Guidance2023-05-15015 May 2023 Automatic RPS Actuation Durin9 Mode 1 Due to Incorrect Relay Settings Caused by Less than Adequate Questioning Attitude, Validation of Assumptions, and Interface/Guidance 05200025/LER-2023-001, Manual Actuation of Reactor Protection System During Mode 3 Due to an Inadequate Procedure Step2023-03-14014 March 2023 Manual Actuation of Reactor Protection System During Mode 3 Due to an Inadequate Procedure Step 05000424/LER-2023-001, Partial Loss of Offsite Power Results in Emergency Diesel Generator and Auxiliary Feedwater Actuation2023-02-27027 February 2023 Partial Loss of Offsite Power Results in Emergency Diesel Generator and Auxiliary Feedwater Actuation 05200025/LER-1922-002-01, Automatic Depressurization System Stage 4 Flow Paths Inoperable During Mode 6 with Upper Internals in Place Due to Inadequate Work Processes2023-02-0303 February 2023 Automatic Depressurization System Stage 4 Flow Paths Inoperable During Mode 6 with Upper Internals in Place Due to Inadequate Work Processes 05200025/LER-2022-003, Unborated Water Flowpath Not Secured Per Technical Specification 3.9.2 Due to Inadequate Procedure Change2022-12-19019 December 2022 Unborated Water Flowpath Not Secured Per Technical Specification 3.9.2 Due to Inadequate Procedure Change 05200025/LER-2022-002, Automatic Depressurization System Stage 4 Flow Paths Inoperable During Mode 6 with Upper Internals in Place Due to Inadequate Work Processes2022-12-19019 December 2022 Automatic Depressurization System Stage 4 Flow Paths Inoperable During Mode 6 with Upper Internals in Place Due to Inadequate Work Processes 05200025/LER-2022-001, Automatic Reactor Trip Signal Due to Inadequate Procedure Guidance Causing Incorrect Opening of Division B DC Supply Breaker2022-12-0202 December 2022 Automatic Reactor Trip Signal Due to Inadequate Procedure Guidance Causing Incorrect Opening of Division B DC Supply Breaker 05000424/LER-2022-001, Manual Reactor Trip Due to Loss of a Main Feed Pump2022-06-24024 June 2022 Manual Reactor Trip Due to Loss of a Main Feed Pump 05000424/LER-2021-001, Train a Safety Injection Pump Inoperability Causes the Unit to Operate in a Condition Prohibited by Technical Specifications2021-11-15015 November 2021 Train a Safety Injection Pump Inoperability Causes the Unit to Operate in a Condition Prohibited by Technical Specifications 05000425/LER-2017-0022017-11-17017 November 2017 Valid Undervottage Condition results in Automatic Actuation of a Safety System, LER 17-002-00 for Vogtle, Unit 2, Regarding Valid Undervoltage Condition Results in Automatic Actuation of a Safety System 05000425/LER-2017-0012017-06-29029 June 2017 1 OF 3, LER 17-001-01 for Vogtle, Unit 2, Regarding Power Supply Failure Results in Operation in a Condition Prohibited by Technical Specifications Supplement 05000424/LER-2017-0022017-06-29029 June 2017 Vice President Vogtle Units 1-2 7821 River RD Waynesboro GA, 30830 706-848-0004 tel 706-848-3321 fax June 29, 2017 Docket No: 50-424 NL-17-1104 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Vogtle Electric Generating Plant — Unit 1 Licensee Event Report 2017-002-01 Wiring Error results in Automatic Actuation of a Safety System Ladies and Gentlemen: In accordance with the requirements of 10 CFR 50.73(a)(2)(iv)(A), Southern Nuclear Operating Company is submitting the enclosed Licensee Event Report, 2017-002-01 for Vogtle Electric Generating Plant Unit 1. This letter contains no NRC commitments. If you have any questions, please contact Dom Sutton at (706) 848-1428. Respectfully sub Darin J. M rs Vice President — Plant ogtle Units 1&2 - SNC DJM/KCW Enclosure: Unit 1 Licensee Event Report 2017-002-01 Cc: Regional Administrator NRR Project Manager — Vogtle 1 & 2 Senior Resident Inspector — Vogtle 1 & 2 RType: CVC7000 Vogtle Electric Generating Plant — Unit 1 Licensee Event Report 2017-002-01 Wiring Labeling Error results in Automatic Actuation of a Safety System Enclosure Unit 1 Licensee Event Report 2017-002-01 NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (04-2017) LICENSEE EVENT REPORT (LER) ILWa t l,viricir (See Page 2 for required number of digits/charactersfor each block) ••••••• (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.qovireadincl-rmidoc-collections/nuregs/staff/sr1022/r3i) APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0313112020 Estimated burden per response to comply with this mandatory collection request: 80 hours Reported lessons learned are incorporated into the licensing process and fed back to industry Send comments regarding burden estimate to the Information Services Branch (T-2 F43), US Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects Resource@nrc gov, and to the Desk Officer, Office of Information •and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington. DC 20503. If a means 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. 1. FACILITY NAME Vogtle Electric Generating Plant . DOCKET NUMBER 13. PAGE 17.:15000424 1 1 OF 2 4. TITLE Mirina Error results in_AulomaticActuation_of a Safety System_, LER 17-002-01 for Vogtle, Unit 1, Wiring Error Results in Automatic Actuation of a Safety System NL-10-0577, LER 10-S01-00 for Vogtle, Units 1 & 2 Regarding Supplemental Worker'S Unescorted Access Not Revoked in a Timely Manner2010-03-30030 March 2010 LER 10-S01-00 for Vogtle, Units 1 & 2 Regarding Supplemental Worker'S Unescorted Access Not Revoked in a Timely Manner 2024-09-05
[Table view] |
LER-2021-001, Train a Safety Injection Pump Inoperability Causes the Unit to Operate in a Condition Prohibited by Technical Specifications |
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Reporting criterion: |
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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4242021001R00 - NRC Website |
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text
~ Southern Nuclear It Or"§yton Pitt§ 7821 Rlvir RD Site Vice Pre ldent WaynelibOfO GA, 30830 V09!1e Unlll> 1-2 106-S4B>oo1n ~J
'iOO*S48*3321 fax Novembe r 15, 2021
U. S. Nuclar Regulatory Commission A TIN : Document Control Desk Washington, D, C, 2055Se0001
Vogt! Electric Gener~ting Pl~nt Unit 1 License~ Event Report 2021 -001e00 1A S~fety Jniection Pump Om~r~tion in ;;J Conditlan Prohibited by Technical Speeiflc~tions
In g!Ceordance with the requirements of 10 CFR 50.73(a)(2)(i){B), Southern Nuclear Opert!lting Company is submitting the ~nclosed License Event Report, 2021 -001 ~00 for Vo9tle gleetrie Generating Plant Unit 1. This letter eontaimi no NRC commitmnm, lf you have g1ny questions, plea~~ contact Jeff 0al ~t (706) 848-3 792.
Respectfully submitted,
Drayton Pitts Site Vice President Vogtle 1&2
RDP/KCW
ec : Regloni!\\!l Administr~tor NRR Project Manager - Vogtle 1 & 2 Senior Resident Inspector= Vogt! 1 & 2 RType : CVC7000 VogtJe EJectri,c Generating Plant Unit 1 Licensee Event Report 2021-001-00.
1A Safety Injection Pump Op.eration in a Condition Prohibited by_ Technical Specifications
Enclosure
Unit 1 Licensee Event Report 2021-001-00
Abstract
On 9/16/2021 at 04 :54, the Unit 1 A Safety Injection (SI) pump was started for a surveillance. Bearing temperatures rose unexpectedly, the pump was stopped, and it was declared inoperable. An investigation found a piece of plastic tubing between the gears of the lube o il pump, resulting in oil starvation of two bearings and their subsequent failure. The bearings were replaced, the system was flushed, and the pump was restored to operable status on September 29, 2021. Improper oil sampling on the Unit 1 Alpha train SI pump introduced foreign material (FM) into the pump's oil system.
The 1A SI pump would not have been able to perform its required safety function from September 6, 202 1 at 1436, until Mode 4 was entered on September 12, 2021 at 0759. Technical Specification (TS) 3.5.2 Condition A should have been entered due to one train of Emergency Core Cooling Systems (ECCS) inoperable. Required Action A.1 has a completion time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or in accordance with the Risk Informed Completion Time Program, combined with 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> for the unit to be in Mode 4, would give 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> of total allowed out of service time. The 137.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that the 1A SI pump would not have been able to perform its required safety function exceeded this, and therefore the plant was operated in a condition prohibited by TS.
A--.---Event Description On 9/16/2021 at 04:54, with plant operating conditions before the event consisting of Unit 1 in Mode 6, at O percent power, and approximately 103 degrees Fahrenh e it, the Unit 1 A Safety Injection (SI) [BQ] pump was started to complete a surveillance. After the pump start, bearing temperatures rose rapidly, the pump was stopped, and was declared inoperable.
Subsequent investigation determined that improper oil sampling on the Unit 1 Alpha train SI pump introduced foreign material (FM) into the pump's oil system. The foreign material introduction was not recognized at the time of the samples. The safety injection pump subsequently failed to operate due to low oil flow conditions resulting in bearing failure. The lube oil pump was found with a piece of plastic tubing between the gears of the pump resulting in the pump seizing.
Timeline of Unit 1 events :
- 9/6/2021 1436-SI pump A was last run during an in-service test (1ST) with no signs of degradation. Additionally, an oil sample was taken during this run.
- 9/12/2021 0500- Unit enters Mode 3 for the start of planned outage.
- 9/12/2021 0759-Unit enters Mode 4, and TS 3.5.2 no longer applied.
- 9/16/2021 0454-SI pump A failed while the unit was in Mode 6.
- 9/29/2021-SI pump A returned to operable status. Unit was in Mode 6, and TS 3.5.2 was not applicable.
The Safety Injection pump would not have been able to perform its required safety function from September 6, 2021 at 1436 when the pump was last run with no signs of degradation, until the mode of applicability for this pump was exited on September 12, 2021 at 0759 due to a planned refueling outage. Technical Specification (TS) 3.5.2 Condition A should have been entered because one train of Emergency Core Cooling Systems (ECCS) was inoperable in Modes 1-
- 3. TS 3.5.2 Required Action A.1 has a completion time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or in accordance with the Risk Informed Completion Time Program. The required act ion time, combined with the 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> for the unit to be in Mode 4, would give 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> of total allowed out of service time. The 137.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that the 1A SI pump would not have been able to perform its required safety function exceeded this allowed out of service time, and therefore the plant was operated in a condition prohibited by TS for 47.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Therefore, this condition is being reported under 10 CFR 50.73(a)(2)(i)(B).
There were no structures, components, or systems that were inoperable at the start of the event that contributed to the event.
B. Cause of Event
The cause of the event was foreign material intrusion into the SI pump oil system. This led the pump outboard bearing to be starved of lubrication which resulted in failure of the bearing when the pump was started.
The foreign material intrusion was caused by improperly obtaining the oil samples for this pump. A plastic tube was inserted into the gearbox next to the oil pump shaft. This caused pieces of the plastic tubing to be removed from the end of the tube and left in the lube oil system.
C. Safety Assessment
During the time the A-train SI pump was inoperable, the 8-train SI pump was available to perform its specified safety function. The operating crew responded correctly to the event. The applicable procedures were properly entered, and documentation met expectations.
The event was within the analysis of the Updated Final Safety Analysis Report Chapter 15. There was no release of radioactivity. This event did not pose a threat to the health and safety of the public. Therefore, the safety significanc e of thi~ i~~110 i~ VP.rv ln\\A/
~D. Corrective Action The failure was corrected by replacement of the bearings, flushing the lube oil system, and restoring the pump to an operable status on September 29, 2021.
The oil sampling method has been changed.
E. Previous Similar Events
None