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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
[Table view] |
LER-2024-001, Inoperable Turbine Stop Valve Limit Switch Causes Condition Prohibited by Technical Specifications |
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text
H Nebraska Public Power District "Always there when you need us"
10 CFR 50.73
NLS2024013 March 4, 2024
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject: Licensee Event Report No. 2024-001-00 Cooper Nuclear Station, Docket No. 50-298, DPR-46
Dear Sir or Madam:
The purpose of this correspondence is to forward Licensee Event Report 2024-001-00.
This letter does not contain regulatory commitments.
Sincerely,
Khalil Dia Site Vice President
/bk
Attachment: Licensee Event Report 2024-001-00
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 / Brownville, NE 68321 http://www.nppd.com
Abstract
During the performance of surveillance testing on January 3, 2024, turbine stop valve (TSV)-1 open limit switch, MS-LMS-SVOS1(1 ), failed to actuate. This failure prevented actuation of the Reactor Protection System (RPS) scram logic for channel A 1. At 0400, Operations declared TSV-1 limit switch inoperable and entered the applicable Technical Specifications (TS) Limiting Condition for Operation (LCO) 12-hour action statement to place the RPS channel in trip and inserting a half-scram.
A pre-planned contingency power reduction was initiated to replace the limit switch. When the switch linkage was disassembled for replacement, the arm was found loose and not fully engaged onto the limit switch shaft.
The switch was replaced, and Operations exited the TS LCO action statement at 0249 on January 4, 2024.
The cause of the failure was due to looseness in the limit switch linkage that attached to the limit switch cam.
This prevented proper engagement to actuate the limit switch when it was exercised for testing.
There were no safety consequences as a result of this event.
PLANT STATUS
Cooper Nuclear Station (CNS) was in Mode 1, Power Operation, at 100 percent power at the time of the event on January 3, 2024.
BACKGROUND
The Reactor Protection System (RPS) [El IS:JC] provides timely protection against the onset and consequences of conditions that threaten the integrity of the fuel barrier and the reactor coolant pressure boundary. The RPS limits the uncontrolled release of radioactive material from the fuel and reactor coolant pressure boundary by terminating excessive temperature and pressure increases through the initiation of an automatic scram.
The RPS includes sensors, relays [EIIS:RL Y], bypass circuits, and switches that are necessary to cause initiation of a reactor [EIIS:RPV] scram. The input parameters to the scram logic are from instrumentation that monitors reactor vessel water level, reactor vessel pressure, neutron flux, main steam line isolation valve position, turbine control valve fast closure, turbine stop valve (TSV) position, drywell pressure, and scram discharge volume water level.
The RPS is arranged as two separately powered trip systems (trip system A and trip system 8). Each trip system has three logics. Two of the logics (A 1, A2; 81, 82) are used to produce automatic trip signals. The input parameters mentioned above are represented by at least one input to each of these logic channels. The remaining logic is used for a manual trip signal. The outputs of the automatic logic channels in a trip system are combined in a "one-out-of-two" logic so that either channel can trip the associated trip system. The tripping of both systems will produce a reactor scram.
The operability of RPS is dependent on the operability of individual instrumentation channel functions specified in Technical Specifications 3.3.1.1, RPS Instrumentation, Table 3.3.1.1-1. For the Turbine Stop Valve-Closure Function (Table 3.3.1.1-1, Function 8), each RPS trip system receives two Turbine Stop Valve-Closure channel inputs from a TSV, each consisting of one position (i.e., limit) switch [EIIS:33] assembly with two contacts, each inputting to a relay. The relays provide a parallel logic input to an RPS trip logic channel. The logic for the Turbine Stop Valve-Closure Function is such that both TSVs must be closed to produce a reactor scram.
Single TSV closure will produce a half scram. Four channels of Turbine Stop Valve-Closure Function, with two channels in each trip system, are required to be operable.
EVENT DESCRIPTION
On January 3, 2024, TSV-1 limit switch MS-LMS-SVOS1 (1 ), failed to actuate during surveillance testing.
Testing of the limit switch function is required to meet Technical Specifications (TS) Surveillance Requirement 3.3.1.1.9 for Table 3.3.1.1-1, Function 8 - TSV Closure. Failure of limit switch MS-LMS-SVOS1 (1) to actuate revented makin u the RPS scram lo ic for channel A1. The other TSV-1 limit switch, MS-LMS-SVOS1 2, 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/readinq-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 001 00
actuated as expected. The safety function of the TSV position limit switches is to initiate a reactor scram at the start of TSV closure. Performance of surveillance testing verifies this function is performing properly.
At 0400, Operations declared TSV-1 limit switch inoperable and entered TS Limiting Condition for Operation (LCO) 3.3.1.1, Condition A, Required Action A.2, place associated trip system in trip, with a Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. At 0853, a pre-planned contingency power reduction to approximately 60% was initiated to replace the limit switch. When the switch linkage was disassembled for replacement, the linkage arm was found partially disengaged from the splined cam of the limit switch. This allowed the arm to move without engaging the limit switch due to it being loose. Additionally, during re-assembly, it was identified the linkage roller did not line up correctly with the TSV actuator arm. The shimming on the limit switch was adjusted to correct the alignment.
Both TSV-1 limit switches, MS-LMS-SVOS1(1) and MS-LMS-SVOS1(2), were replaced and Operations exited LCO 3.3.1.1, Condition A, on January 4, 2024, at 0249 hours0.00288 days <br />0.0692 hours <br />4.117063e-4 weeks <br />9.47445e-5 months <br />.
MS-LMS-SVOS 1 ( 1) Performance History:
The failed TSV-1 limit switch was previously installed under the normal preventive maintenance (PM) frequency in October 2020 during refueling outage 31. The PM work order replaced both TSV-1 limit switches. Functional testing was conducted during quarterly power reductions the following operating cycle with no issues identified.
In November 2022, during refueling outage 32, MS-LMS-SVOS1 (1) was removed to support work on TSV-1 and reinstalled. Online functional testing continued during quarterly power reductions with no issues documented for the 2023 first or second quarter tests.
During TSV-1 limit switch functional testing on August 19, 2023, MS-LMS-SVOS1(1) was slow to actuate. At the time, it was determined the delayed response was due to the method of testing and that the switch lever was not fully actuated far enough to change state of the limit switch. The station operator performing the test noted that while actuating the switch, they had to reposition their body to get full engagement. When they repositioned, the switch did actuate to drop out the associated relays. An additional test was performed by a different individual to ensure the switch was fully actuated and testing was completed successfully. TSV-1 limit switch MS-LMS-SVOS1(2) performed as expected. During the testing, both limit switches on TSV-2 actuated correctly.
TSV-1 limit switch testing was again performed on November 18, 2023. During this testing, limit switch MS-LMS-SVOS1 (1) did not change state. The switch lever mechanism was held for approximately five minutes with no change. MS-LMS-SVOS1 (2) actuated as expected. As a result of this testing, Maintenance personnel visually inspected the switch and Engineering personnel evaluated the condition. An additional test was performed with a scope recorder connected to the associated relays to assist with diagnostics. During this test, the relays performed as expected. Based on the successful test, visual inspections, and experience from previous switch failure, it was a ain sus ected the initial test failure was associated with how the testin was 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/readinq-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 001 00
performed; by not fully engaging the switch mechanism causing it to change state. During the testing, both limit switches on TSV-2 actuated correctly.
The functional testing performed on January 3, 2024, was done at an increased frequency (from quarterly to a 6-week interval) based on previous test performance of limit switch MS-LMS-SVOS1(1) and industry operating experience that identified the potential for grease hardening in the switch mechanism. Results from subsequent lab analysis performed on the failed limit switch ruled out grease hardening as a potential failure mode.
The switch linkage arm looseness that was identified following MS-LMS-SVOS1 (1) failure on January 3, 2024, was not identified during the previous inspection on November 18, 2023. It cannot be determined if the looseness was present at that time. Linkage arm looseness can only be observed by looking for a gap on the top side of the switch and linkage. The engagement of the linkage on to the cam cannot be seen since the linkage covers the cam. The testing method of manually cycling the limit switch has been performed at CNS for over 20 years as an acceptable practice with consistent good responses.
The installed limit switches for TSV-1 and TSV-2 are Namco, series EA740.
BASIS FOR REPORT
Based on performance history of limit switch MS-LMS-SVOS1(1 ), the TSV-1 was inoperable back to the date of the initial failed surveillance, i.e., on August 19, 2023. As such, this event is reportable under 10 CFR 50.73(a)(2)(i)(B) -Any operation or condition which was prohibited by TS.
SAFETY SIGNIFICANCE
There were no safety consequences as a result of this event. The failure to actuate was only experienced on one TSV-1 limit switch MS-LMS-SVOS1 (1 ). During the time the TSV-1 closure function was inoperable for this failure, there was no failure of the other limit switch for TSV-1, nor was there any failure of the two limit switches for TSV-2. Therefore, a closure of TSV-1 would still have generated a half scram signal on RPS channel A2 and a normal half scram would have been generated from both Channels 81 and 82 for TSV-2 closure.
CAUSES
The mechanistic cause for the failure of the limit switch to actuate during testing was due to the assembly and alignment of the linkage mechanism not having full engagement on the splined cam.
A contributing cause was that the installation guidance did not contain the necessary vendor manual information to ensure consistency for tightening linkage to the cam shaft. The guidance also did not have detail for aligning the linkage to the actuator which allowed it to disengage from the spline adaptor and prevented the limit switch from actuatin 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:
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Cooper Nuclear Station 05000-298 NUMBER NO.
2024 001 00
CORRECTIVE ACTIONS
MS-LMS-SVOS 1 ( 1) was replaced using additional vendor guidance and detail to perform shimming for proper alignment.
CNS will also update the associated maintenance plans to include additional instruction on tightening limit switches, shimming as necessary for alignment, and to manually stroke the linkage.
PREVIOUS EVENTS
There have been no previous events in the last three years regarding TSV limit switch failures other than that discussed in the Event Description section of this report.