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Category:Letter
MONTHYEARIR 05000298/20240032024-11-0505 November 2024 Integrated Inspection Report 05000298/2024003 ML24250A2052024-10-0808 October 2024 Issuance of Amendment No. 278 Regarding Revision to Technical Specification Table 3.3.2.1-1 and Transfer of Minimum Critical Power Ratio Values to Core Operating Limit Report ML24227A0822024-09-0303 September 2024 Summary of Regulatory Audit in Support of License Amendment Request to Modify the High Pressure Coolant Injection Low Flow Value IR 05000298/20240052024-08-22022 August 2024 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2024005) IR 05000298/20240022024-07-25025 July 2024 Integrated Inspection Report 05000298/2024002 ML24183A1722024-07-17017 July 2024 Issuance of Amendment No. 277 to Adopt TSTF-374, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil ML24197A1462024-07-15015 July 2024 NRC Region IV Ltr to Cooper Nuclear Station Re FEMA Level 1 Finding ML24134A1782024-07-0303 July 2024 Issuance of Amendment No. 276 Revision to Technical Specification 3.8.3, Diesel Fuel Oil, Lube Oil and Starting Air, to Allow for Cleaning, Inspection and Any Needed Repairs During Refuel Outage 33 ML24197A0682024-06-24024 June 2024 FEMA Ltr to Missouri State Emergency Management Agency - Level 1 Finding, 24 June 2024 ML24192A0112024-06-13013 June 2024 2024-06-Post Exam Comments 05000298/LER-2023-002-01, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2024-06-0606 June 2024 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications IR 05000298/20244012024-06-0404 June 2024 Security Baseline Inspection Report 05000298/2024401 ML24151A1082024-05-30030 May 2024 NRC Initial Operator Licensing Examination Approval 05000298/2024301 ML24137A0942024-05-17017 May 2024 Regulatory Audit Plan in Support of License Amendment Request to Modify Allowable Value Regarding Technical Specification for High Pressure Coolant Injection Pump Discharge Low Flow 05000298/LER-2024-005, High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical2024-05-13013 May 2024 High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical. 05000298/LER-2024-004, Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications2024-05-0909 May 2024 Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications IR 05000298/20240012024-05-0303 May 2024 Integrated Inspection Report 05000298/2024001 ML24129A0952024-04-25025 April 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000298/20240102024-04-24024 April 2024 Comprehensive Engineering Team Inspection Report 05000298/2024010 05000298/LER-2024-003, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications2024-04-22022 April 2024 High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications ML24096A1202024-04-0505 April 2024 Issuance of Amendment No. 275 Revision to Technical Specification 3.3.1.1 (Emergency Circumstances) ML24093A2282024-04-0202 April 2024 Notice of Enforcement Discretion for Cooper Nuclear Station IR 05000298/20240902024-04-0101 April 2024 – Notice of Violation, NRC Inspection Report 05000298/2024090 05000298/LER-2024-001, Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications2024-03-0404 March 2024 Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications 05000298/LER-2024-002, Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump2024-03-0404 March 2024 Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump IR 05000298/20230062024-02-28028 February 2024 Annual Assessment Letter for Cooper Nuclear Station - Report 05000298/2023006 IR 05000298/20230042024-02-12012 February 2024 Integrated Inspection Report 05000298/2023004 ML24033A3092024-02-12012 February 2024 Summary of Regulatory Audit Regarding the Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20230122024-02-12012 February 2024 NRC Inspection Report 05000298/2023012 ML23334A2012024-01-0303 January 2024 Issuance of Amendment No. 274 Revision to Technical Specifications to Adopt TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements 05000298/LER-2023-002, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2023-12-20020 December 2023 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications 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 ML23311A1122023-11-0909 November 2023 Project Manager Assignment IR 05000298/20230032023-11-0202 November 2023 Integrated Inspection Report 05000298/2023003 IR 05000298/20234012023-11-0101 November 2023 Cyber Security Report 05000298/2023401 Public ML23264A8052023-10-11011 October 2023 Issuance of Amendment No. 273 Revision to Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23233A1882023-09-0505 September 2023 Regulatory Audit Plan in Support of Relief Request RC3-02 Regarding Drywell Head Bolting IR 05000298/20243012023-09-0101 September 2023 Notification of NRC Initial Operator Licensing Examination 05000298/2024301 IR 05000298/20230052023-08-21021 August 2023 Updated Inspection Plan for Cooper Nuclear Station (Report 05000298/2023005)- Mid Cycle Letter IR 05000298/20230022023-08-0808 August 2023 Integrated Inspection Report 05000298/2023002 IR 05000298/20234022023-08-0303 August 2023 NRC Security Inspection Report 05000298/2023402 ML23214A2742023-08-0303 August 2023 Nuclear Station - Notification of Inspection (NRC Inspection Report 05000298/2023004) and Request for Information IR 05000298/20234202023-08-0101 August 2023 Security Baseline Inspection Report 05000298/2023420 05000298/LER-2022-002-01, Manual Core Spray Injection to Restore Skimmer Surge Tank Level2023-06-29029 June 2023 Manual Core Spray Injection to Restore Skimmer Surge Tank Level ML23173A0862023-06-26026 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000298/2023401 IR 05000298/20230102023-05-17017 May 2023 Biennial Problem Identification and Resolution Inspection Report 05000298/2023010 05000298/LER-2022-004-01, 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open2023-05-11011 May 2023 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open 05000298/LER-2023-001, Valve Test Failures Result in Condition Prohibited by Technical Specifications2023-05-0808 May 2023 Valve Test Failures Result in Condition Prohibited by Technical Specifications IR 05000298/20234032023-05-0404 May 2023 Security Baseline Inspection Report 05000298/2023403 ML23129A2822023-04-20020 April 2023 Submittal of Revision 31 to Updated Safety Analysis Report 2024-09-03
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000298/LER-2023-002-01, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2024-06-0606 June 2024 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications 05000298/LER-2024-005, High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical2024-05-13013 May 2024 High Pressure Coolant Injection Pressure Switch Installation Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited B Technical. 05000298/LER-2024-004, Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications2024-05-0909 May 2024 Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications NLS2024035, Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications2024-05-0909 May 2024 Main Turbine Stop Valve Position Switches Do Not Meet Channel Independence Criteria Results in Two Channels Being Declared Inoperable and a Condition Prohibited by Technical Specifications 05000298/LER-2024-003, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications2024-04-22022 April 2024 High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications 05000298/LER-2024-002, Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump2024-03-0404 March 2024 Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump 05000298/LER-2024-001, Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications2024-03-0404 March 2024 Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications 05000298/LER-2023-002, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications2023-12-20020 December 2023 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications 05000298/LER-2022-002-01, Manual Core Spray Injection to Restore Skimmer Surge Tank Level2023-06-29029 June 2023 Manual Core Spray Injection to Restore Skimmer Surge Tank Level 05000298/LER-2022-004-01, 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open2023-05-11011 May 2023 1 for Cooper Nuclear Station, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open 05000298/LER-2023-001, Valve Test Failures Result in Condition Prohibited by Technical Specifications2023-05-0808 May 2023 Valve Test Failures Result in Condition Prohibited by Technical Specifications 05000298/LER-2022-004, Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open2023-02-14014 February 2023 Manual Reactor Scram and Group I Isolation Due to Main Turbine Bypass Valve Failing Open 05000298/LER-2022-003, Actuation of Reactor Protection System Initiates a Full Reactor Scram2023-01-11011 January 2023 Actuation of Reactor Protection System Initiates a Full Reactor Scram 05000298/LER-2022-002, Manual Core Spray Injection to Restore Skimmer Surge Tank Level2022-12-19019 December 2022 Manual Core Spray Injection to Restore Skimmer Surge Tank Level 05000298/LER-2022-001, Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications Limit2022-07-20020 July 2022 Secondary Containment Differential Pressure Perturbation Exceeds Technical Specifications Limit 05000298/LER-2021-003, Re Failure of High Pressure Coolant Injection Flow Indicating Switch Results in Condition Prohibited by Technical Specifications2021-12-27027 December 2021 Re Failure of High Pressure Coolant Injection Flow Indicating Switch Results in Condition Prohibited by Technical Specifications 05000298/LER-2016-0012017-09-27027 September 2017 De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused by Relay Failure Results in Loss of Safety Function and a Condition Prohibited by Technical Specifications, LER 16-001-01 for Cooper Nuclear Station Regarding De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused by Relay Failure Results in Loss of Safety Function, a Condition Prohibited by Tech Specs, and a 10 CFR Part 21 Report 05000298/LER-2017-0052017-08-17017 August 2017 Traversing In-core Probe In-shield Limit Switch Mounting Failure Results in Common Cause Inoperability of Independent Trains or Channels and Condition Prohibited by Technical Specifications, LER 17-005-00 for Cooper Nuclear Station Regarding Traversing In-core Probe In-shield Limit Switch Mounting Failure Results in Common Cause lnoperability of Independent Trains or Channels and Condition Prohibited by Technical Specifications 05000298/LER-2017-0042017-08-17017 August 2017 Torus to Drywell Vacuum Breaker Failure to Indicate Full Closed Causes Loss of Safety Function, LER 17-004-00 for Cooper Nuclear Station Regarding Torus to Drywall Vacuum Breaker Failure to Indicate Full Closed Causes Loss of Safety Function 05000298/LER-2017-0032017-07-24024 July 2017 Mispositioned Control Room Emergency Filter System Supply Fan Damper Causes Loss of Safety Function, LER 17-003-00 for Cooper Nuclear Station re Mispositioned Control Room Emergency Filter System Supply Fan Damper Causes Loss of Safety Function 05000298/LER-2017-0022017-04-27027 April 2017 Valve Test Failures Result in Condition Prohibited by Technical Specifications and a Loss of Safety Function, LER 17-002-00 for Cooper Nuclear Station Regarding Valve Test Failures Result in Condition Prohibited by Technical Specifications and a Loss of Safety Function 05000298/LER-2017-0012017-04-0505 April 2017 Residual Heat Removal Minimum Flow Valves OUt of Position Results in Loss of Safety Function and Condition Prohibited by Technical Specifications, LER 17-001-00 for Cooper Regarding Residual Heat Removal Minimum Flow Valves Out of Position Results in Loss of Safety Function and Condition Prohibited by Technical Specifications 05000298/LER-2016-0082017-01-0505 January 2017 Purchase and Installation of Incorrect Actuator Results in a Condition Prohibited by Technical Specifications, LER 16-008-00 for Cooper Nuclear Station Regarding Purchase and Installation of Incorrect Actuator Results in a Condition Prohibited by Technical Specifications 05000298/LER-2016-0062016-12-19019 December 2016 High Vibration on Control Room Emergency Filter System Fan Results in Inoperability and Loss of Safety Function, LER-16-006-00 for Cooper Nuclear Station Regarding High Vibration on Control Room Emergency Filter System Fan Results in Inoperability and Loss of Safety Function 05000298/LER-2016-0072016-12-19019 December 2016 Isolation of Shutdown Cooling due to Relay Maintenance Results in a Loss of Safety Function, LER 16-007-00 for Cooper Nuclear Station Regarding Isolation of Shutdown Cooling due to Relay Maintenance Results in a Loss of Safety Function 05000298/LER-2016-0042016-11-22022 November 2016 Closure of Multiple Main Steam Isolation Valves due to High Flow Signal, LER 16-004-00 for Cooper Nuclear Station Regarding Closure of Multiple Main Steam Isolation Valves due to High Flow Signal 05000298/LER-2016-0032016-11-0909 November 2016 Scaffold Construction Places Plant in a Condition Prohibited by Technical Specifications, LER 16-003-00 for Cooper Nuclear Station RE: Scaffold Construction Places Plant in a Condition Prohibited by Technical Specifications 05000298/LER-2016-0022016-06-27027 June 2016 De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused By Light Bulb Failure Results in Loss of Safety Function, LER 16-002-00 for Cooper Regarding De-Energized High Pressure Coolant Injection Auxiliary Lube Oil Pump Caused By Light Bulb Failure Results in Loss of Safety Function NLS2015063, Retraction of Licensee Event Report 2014-005-00, Lube Oil Leak Results in a Potential Condition Prohibited by Technical Specifications and a Potential Loss of Safety Function.2015-06-0909 June 2015 Retraction of Licensee Event Report 2014-005-00, Lube Oil Leak Results in a Potential Condition Prohibited by Technical Specifications and a Potential Loss of Safety Function. ML13149A1722013-05-26026 May 2013 E-mail from Micheal Mulligan to R.Guzman, Pilgrim Evacuation Plan Broken During Blizzard Nemo and Unenforced by the Nrc. NLS2013015, Special Report, Offgas Treatment System Charcoal Adsorbers Out of Service2013-01-29029 January 2013 Special Report, Offgas Treatment System Charcoal Adsorbers Out of Service NLS2008058, LER 08-S01-00 for Cooper Regarding Temporary Suspension of Security Measures Due to Tornado Warning2008-08-0505 August 2008 LER 08-S01-00 for Cooper Regarding Temporary Suspension of Security Measures Due to Tornado Warning 2024-06-06
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LER-2024-002, Technical Specifications Prohibited Condition for Inoperable Service Water Booster Pump |
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H Nebraska Public Power District "Always there when you need us"
10 CFR 50.73
NLS2024014 March 4, 2024
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject: Licensee Event Report No. 2024-002-00 Cooper Nuclear Station, Docket No. 50-298, DPR-46
Dear Sir or Madam:
The purpose of this correspondence is to forward Licensee Event Report 2024-002-00.
This letter does not contain regulatory commitments.
Sincerely,
Khalil Dia Site Vice President
/bk
Attachment: Licensee Event Report 2024-002-00
cc: Regional Administrator w/attachment NPG Distribution w/attachment USNRC - Region IV
Cooper Project Manager w/attachment INPO Records Center w/attachment USNRC - NRR Plant Licensing Branch IV via IRIS entry
Senior Resident Inspector w/attachment SORC Chairman w/attachment USNRC-CNS
SRAB Administrator w/attachment CNS Records w/attachment
COOPER NUCLEAR STATION 72676 648A Ave/ P.O. Box 98 I Brownville, NE 68321 http://www.nppd.com
Abstract
On August 27, 2022, Residual Heat Removal Service Water Booster pump 'D' (SW-P-BPD) outboard pump bearing temperature reached the high warning temperature alarm. Upon investigation of the alarm, a three drops per minute oil leak was observed on the pump inboard, radial bearing. At 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br />, Operations declared SW-P-BPD inoperable and entered the applicable Technical Specification Limiting Condition for Operation.
The pump bearing oil leakage was repaired and both inboard and outboard booster pump bearings replaced.
SW-P-BPD was declared operable at 1614 on September 1, 2022.
The cause of the pump inboard bearing oil leakage was a fabrication issue by the original pump manufacturer.
The cause of the pump thrust bearing elevated temperature was that the maintenance procedure used for the previous pump rebuild in July 2022 was not as detailed in accordance with the original manufacturer's recommendations with respect to installation of the pump thrust bearing.
There were no safety consequences as a result of this event.
PLANT STATUS
At the time of the event on August 27, 2022, Cooper Nuclear Station (CNS) was in Mode 1, Power Operation, at 81 percent power for end-of-cycle power coast down.
BACKGROUND
The Residual Heat Removal [EIIS:BO] Service Water Booster (RHRSWB) system is designed to provide cooling water for the Residual Heat Removal system (RHR) heat exchangers [EIIS:HX], required for a safe reactor shutdown following a Design Basis Accident or transient. The RHRSWB system is operated whenever the RHR heat exchangers are required to operate in the shutdown cooling or suppression pool cooling mode.
The system is initiated manually from the Control Room. If operating during a loss of coolant accident (LOCA),
the system is automatically tripped to allow the diesel generators [EIIS:DG] to automatically power only that equipment necessary to reflood the core.
The RHRSWB system removes heat from the suppression pool via the RHR system to limit the suppression pool temperature and primary containment [EIIS:NH] pressure following a LOCA. This ensures that the primary containment can perform its function of limiting the release of radioactive materials to the environment following a LOCA.
The RHRSWB system consists of two independent and redundant subsystems. Each subsystem is made up of a header, two pumps [EIIS:P], a suction source, valves, piping, heat exchanger, and associated instrumentation. Two RHRSWB pumps per subsystem are required to be operable to satisfy the requirements of Technical Specifications (TS), Limiting Condition for Operation (LCO) 3.7.1.
EVENT DESCRIPTION
RHRSWB pump 'D' (SW-P-BPD) was removed from service at 0202 ~ours on July 27, 2022, and was replaced as part of routine preventive maintenance. SW-P-BPD was restored to operable status after this replacement at 0333 hours0.00385 days <br />0.0925 hours <br />5.505952e-4 weeks <br />1.267065e-4 months <br /> on July 29, 2022.
On August 27, 2022, at approximately 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, SW-P-BPD was placed in service to support SW chemical injection to control zebra mussels within the SW system. At approximately 1942 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.38931e-4 months <br />, a high thrust bearing temperature alarm was received on the Plant Management Information System (PMIS). While investigating the condition, a separate oil leak of three drops per minute (dpm) was observed on the pump inboard radial bearing, and a one dpm oil leak observed on the pump outboard thrust bearing. Due to the excessive oil leakage of the pump inboard bearing and pump outboard bearing high temperature, Operations declared SW-P-BPD inoperable at 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br /> and entered TS LCO 3.7.1, Condition A, Required Action A.1, to restore SW-P-BPD to operable status within 30 da s. NRC FORM 366A (10-01-2023) U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2024 Estimated burden per response to comply with this mandatory collection request:
80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process LICENSEE EVENT REPORT (LER) and fed back to industry. Send comments regarding burden estimate to the FOIA, CONTINUATION SHEET Library, and Information Collections Branch (T-6 A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email to lnfocollects.Resource@nrc.gov, and the 0MB reviewer at: 0MB Office of Information and Regulatory Affairs, (3150-0104 ), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, Washington, DC 20503; email:
(See NUREG-1022, R.3 for instruction and guidance for completing this form oira submission@omb.eop.gov. The NRC may not conduct or sponsor, and a http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/) person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid 0MB control number.
Cooper Nuclear Station 05000-298 NUMBER NO.
2024 002 00
On August 28, 2022, SW-P-BPD was placed in service for troubleshooting. Validation of the outboard bearing high temperature condition included obtaining vibration data, an oil sample, and thermography. The thermography reading confirmed the abnormal temperature condition was valid. The oil was black with evidence of degradation having occurred. Further offsite analysis confirmed the oil contained elevated particulate levels and contained visible debris. Subsequent discussions with maintenance personnel and review of the maintenance history and manufacturer's recommendations contained in the associated vendor manual revealed that during the July 2022 pump replacement activity, the thrust bearing locknut was overtightened resulting in more pre-loading of the bearing. That pre-load added to the thrust load during subsequent SW-P-BPD operations resulting in further degradation of the load-bearing surfaces of the bearing causing the bearing's elevated temperatures. Maintenance history and PMIS data was searched back to 1993 with no previous instances of elevated outboard thrust bearing temperature found.
Further investigation of the inboard bearing oil leak involved disassembly and inspection of the pump.
The oil leakage was identified from where the pump shaft protrudes through the inboard bearing cover. The original manufacturer, Byron Jackson (Flowserve), was contacted to review photographs of the cover. A discrepancy was identified with configuration of the labyrinth seal drain path. The as-machined configuration did not allow the outer groove to drain back to the oil reservoir because the angled drain slot was machined incorrectly. This discrepancy was due to an error introduced when the associated fabrication drawings were updated in 2012, just prior to manufacture of the pump. This improper fabrication of the angled drain slot in the inboard bearing cover labyrinth seal caused the oil leak. The other three installed RHRSWBPs were also procured under the same contract as SW-P-BPD. No oil leakage was observed from these pumps.
Corrective maintenance was performed to replace both the inboard and outboard pump bearings and the inboard bearing cover with one that was machined prior to the manufacturer's 2012 drawing update.
At 1614 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.14127e-4 months <br /> on September 1, 2022, following successful post-work testing and an approximate 12-hour pump run, SW-P-BPD was declared operable and TS LCO 3.7.1, Condition A, was exited.
BASIS FOR REPORT
On January 4, 2024, CNS Licensing personnel discovered that a back-end review of the causal report for this equipment condition was required but had not been completed. This condition was entered into the station's corrective action program. A review was completed and concluded there was firm evidence that SW-P-BPD was inoperable for greater than the completion time permitted by TS (30 days) based on the operating conditions of the thrust bearing in combination with the expected environmental conditions during a design basis event.
Based on this information, SW-P-BPD was inoperable from July 27, 2022, until September 1, 2022, for a total duration of 36 days. TS LCO 3. 7.1, Condition A, one RHRSWB pump inoperable, applies which has a completion time of 30 days. Based on exceeding the TS completion time, this event is reportable under 10 CFR 50. 73 a 2 i B as an operation or condition which was prohibited b TS. NRC FORM 366A (10-01-2023) U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2024 Estimated burden per response to comply with this mandatory collection request:
80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />. Reported lessons learned are incorporated into the licensing process LICENSEE EVENT REPORT (LER) and fed back to industry. Send comments regarding burden estimate to the FOIA, CONTINUATION SHEET Library, and Information Collections Branch {T-6 A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email to lnfocollects.Resource@nrc.gov, and the 0MB reviewer at: 0MB Office of Information and Regulatory Affairs, (3150-0104 ), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, Washington, DC 20503; email:
(See NUREG-1022, R.3 for instruction and guidance for completing this form oira submission@omb.eop.gov. The NRC may not conduct or sponsor, and a http://www.nrc.gov/reading-rm/doc-collections/nureqs/staff/sr1022/r3/) person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid 0MB control number.
Cooper Nuclear Station 05000-298 NUMBER NO.
2024 002 00
SAFETY SIGNIFICANCE
There were no safety consequences as a result of this event. The RHRSWB system is designed with sufficient redundancy so that no single active system component failure nor any single active component failure in any other plant system can prevent it from achieving its safety objective. Two independent loops are provided, each capable of full design capacity with only one pump available. During the time of SW-P-BPD inoperability, RHRSWB pump 'B' was operable or the Division 1 RHRSWB subsystem (pumps 'A' and 'C') was operable.
The operability of one of these two options maintained the safety function for the duration when SW-P-BPD was inoperable. As such, there was no loss of safety function.
CAUSE
This event involved two separate, unrelated SW-P-BPD equipment issues and separate causal factors were determined for each.
The cause of the elevated outboard bearing temperature was the maintenance procedure used for pump rebuild was not as detailed in accordance with the original manufacturer's recommendations for installation of the pump thrust bearing; specifically, the tightening of the thrust bearing locknut.
The cause of the inboard bearing oil leak was a fabrication issue by the pump original manufacturer.
CORRECTIVE ACTIONS
As discussed above, maintenance personnel repaired the pump thrust bearing and bearing oil leakage.
Other corrective actions taken were:
- Revised the maintenance procedure for RHRSWB pump overhaul/replacement to add guidance for ensuring thrust bearing installation is in accordance with vendor recommendations.
- Revised the maintenance procedure for RHRSWB pump overhaul/replacement to add guidance for inspection of the labyrinth bearing seals to verify the drain path is configured in accordance with manufacturer design requirements.
These actions are complete.
PREVIOUS EVENTS
There have been no events reported in the past three years related to the RHRSWB system.