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Category:Letter
MONTHYEARML24352A2612024-12-18018 December 2024 Notification of Licensed Operator Initial Examination 05000250/2025302 and 05000251/2025302 ML24344A0772024-12-12012 December 2024 Authorized Alternative to Requirements of the American Society of Mechanical Engineers Operation and Maintenance Code L-2024-199, Special Report - Post Accident Monitoring Instrumentation2024-12-10010 December 2024 Special Report - Post Accident Monitoring Instrumentation L-2024-191, Reply to a Notice of Violation: NOV 05000250/2024003 and 05000251/20240032024-11-22022 November 2024 Reply to a Notice of Violation: NOV 05000250/2024003 and 05000251/2024003 IR 05000250/20240032024-11-13013 November 2024 Integrated Inspection Report - 05000250/2024003 & 05000251/2024003 & Notice of Violation L-2024-187, Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-11-12012 November 2024 Supplement to the Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-188, Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-11-12012 November 2024 Supplement to License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24305A1482024-11-0606 November 2024 Westinghouse Topical Report - Request for Withholding Information from Public Disclosure L-2024-184, Radiological Emergency Plan Revision 772024-11-0505 November 2024 Radiological Emergency Plan Revision 77 ML24276A2162024-11-0101 November 2024 Request for Withholding Information from Public Disclosure L-2024-173, Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-31031 October 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums ML24291A2882024-10-24024 October 2024 Westinghouse Topical Report - Request for Withholding Information from Public Disclosure L-2024-175, Cycle 34 Core Operating Report2024-10-24024 October 2024 Cycle 34 Core Operating Report L-2024-177, Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis2024-10-22022 October 2024 Revised Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24276A2302024-10-16016 October 2024 Westinghouse Topical Report – Request for Withholding Information from Public Disclosure ML24289A2372024-10-15015 October 2024 Transmittal of Revision 1 Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-157, Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles2024-10-0303 October 2024 Response to Requests for Additional Information Regarding License Amendment Request (278) to Facilitate a Transition to 24-Month Fuel Cycles IR 05000250/20243012024-10-0303 October 2024 NRC Operator License Examination Report 05000250/2024301 and 05000251/2024301 L-2024-147, Submission of Periodic Reports2024-10-0101 October 2024 Submission of Periodic Reports L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24269A1292024-09-24024 September 2024 Response to Requests for Additional Information Regarding Turkey Point License Amendment Request 277, Updated Spent Fuel Pool Criticality Analysis ML24260A2262024-09-18018 September 2024 NRC Examination Results Summary - Examination Reports: 05000250/2024301 and 05000251/2024301 ML24262A2272024-09-18018 September 2024 Transmittal of Additional Errata Pages for WCAP-18830-P (Proprietary) and WCAP-18830-NP (Non-Proprietary), Turkey Point Fuel Storage Criticality Analysis for 24 Month Cycles ML24158A0052024-09-17017 September 2024 Completion of Subsequent License Renewal Site Specific Environmental Review and Modification to Subsequent Renewed Facility Operating Licenses L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24207A0342024-09-13013 September 2024 – Exemption from Certain Requirements of 10 CFR 50.46 for Use of Axiom Fuel Rod Cladding – Letter ML24256A1132024-09-13013 September 2024 Regulatory Audit Summary Related to the Review of Regarding the Updated Spent Fuel Pool Criticality Safety Analysis License Amendment Request IR 05000250/20240052024-08-23023 August 2024 Updated Inspection Plan for Turkey Point Units 3 & 4 - Report 05000250/2024005 and 05000251/2024005 ML24234A0062024-08-22022 August 2024 Project Manager Assignment L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report IR 05000250/20240112024-08-0606 August 2024 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000250/2024011 and 05000251/2024011 ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan 05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal ML24173A1902024-06-28028 June 2024 Withdrawal of an Amendment Request ML24159A2652024-06-26026 June 2024 Correction of Safety Evaluation for Issuance of Amendment Nos. 298 & 291 Regarding Revising the Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter IR 05000250/20244012024-06-0505 June 2024 – Security Baseline Inspection Report 05000250-2024401, 05000251-2024401 and 07200062-2024401 L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report 2024-09-25
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000250/LER-2024-002-01, Condition Prohibited by Technical Specifications2024-07-10010 July 2024 Condition Prohibited by Technical Specifications 05000250/LER-2024-002, 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications2024-04-11011 April 2024 0 for Turkey Point, Unit 3 - Condition Prohibited by Technical Specifications 05000250/LER-2023-004, Unplanned Automatic Scram During RPS Testing2023-12-13013 December 2023 Unplanned Automatic Scram During RPS Testing 05000250/LER-2023-003, Grid Disturbance in Switchyard Causes Automatic Reactor Trip2023-11-20020 November 2023 Grid Disturbance in Switchyard Causes Automatic Reactor Trip ML23318A1782023-11-13013 November 2023 FAQ 23-03- Turkey Point IE01 05000250/LER-2023-002, Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure2023-10-0202 October 2023 Manual Reactor Trip Due to Steam Generator Feedwater Regulating Valve Positioner Failure 05000250/LER-2023-001, RCS Pressure Boundary Degraded2023-06-14014 June 2023 RCS Pressure Boundary Degraded 05000250/LER-2021-003, Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown2021-12-0202 December 2021 Regarding Auxiliary Feedwater Actuation Due to Feedwater Isolation During Plant Shutdown 05000250/LER-2021-002, Unrecognized Technical Specification Surveillance Requirement Non-Compliance2021-06-0303 June 2021 Unrecognized Technical Specification Surveillance Requirement Non-Compliance 05000250/LER-2021-001, Automatic Reactor Trip Due to Reactor Trip Breaker Cell Switch Malfunction2021-04-29029 April 2021 Automatic Reactor Trip Due to Reactor Trip Breaker Cell Switch Malfunction 05000250/LER-2020-005-01, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (Rev 1)2021-03-0505 March 2021 Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel (Rev 1) 05000250/LER-2020-002-01, Manual Reactor Trip in Response to High Steam Generator Level Following Inadve1ient Opening of Feedwater Heater Bypass Valve (Rev 1)2021-03-0505 March 2021 Manual Reactor Trip in Response to High Steam Generator Level Following Inadve1ient Opening of Feedwater Heater Bypass Valve (Rev 1) 05000250/LER-2020-005, Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel2020-10-14014 October 2020 Technical Specification Action Not Taken for Unrecognized Inoperable Source Range Channel 05000250/LER-2020-004, Re Manual Reactor Trip in Response to Automatic Trip of the 3B Steam Generator Feedwater Pump2020-10-0707 October 2020 Re Manual Reactor Trip in Response to Automatic Trip of the 3B Steam Generator Feedwater Pump 05000250/LER-2020-003, Automatic Reactor Trip Due to High Source Range Flux During Reactor Startup2020-09-29029 September 2020 Automatic Reactor Trip Due to High Source Range Flux During Reactor Startup 05000250/LER-2020-002, Re Manual Reactor Trip in Response to High Steam Generator Level Following Inadvertent Opening of Feedwater Heater Bypass Valve2020-09-23023 September 2020 Re Manual Reactor Trip in Response to High Steam Generator Level Following Inadvertent Opening of Feedwater Heater Bypass Valve 05000251/LER-2020-001, Automatic Reactor Trip Caused by Main Generator Lockout Due to Exciter Fault2020-08-28028 August 2020 Automatic Reactor Trip Caused by Main Generator Lockout Due to Exciter Fault 05000250/LER-2020-001, Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units2020-06-24024 June 2020 Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrument Channel Functional Units L-2019-127, Manual Reactor Trip Following Grid Disturbance2019-06-27027 June 2019 Manual Reactor Trip Following Grid Disturbance 05000250/LER-2018-002, As-Found Cycle 29 Main Steam Safety Valve Setpoints Outside Technical Specification Limits2018-11-21021 November 2018 As-Found Cycle 29 Main Steam Safety Valve Setpoints Outside Technical Specification Limits 05000250/LER-2018-001, Inoperable Containment Purge Exhaust Penetration2018-11-21021 November 2018 Inoperable Containment Purge Exhaust Penetration 05000251/LER-2018-001, Inoperable Auxiliary Feedwater Steam Supply Flowpath2018-06-27027 June 2018 Inoperable Auxiliary Feedwater Steam Supply Flowpath 05000251/LER-1917-001, Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control2017-11-0707 November 2017 Regarding Manual Reactor Trip Due to Lowering Steam Generator Level Caused by Loss of Flow Regulating Valve Positioner Control 05000250/LER-1917-001, Regarding Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations, and Loss of Safety Injection Function2017-05-16016 May 2017 Regarding Loss of 3A 4kV Vital Bus Results in Reactor Trip, Safety System Actuations, and Loss of Safety Injection Function L-2017-090, LER Special Report Regarding Accident Monitoring Instrumentation2017-05-11011 May 2017 LER Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2016-001, Regarding Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection Instrument Channel2016-06-30030 June 2016 Regarding Technical Specification Action Not Taken for Unrecognized Inoperable Reactor Protection Instrument Channel 05000250/LER-2016-001, Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to Be Inoperable Longer than Allowed2016-04-0707 April 2016 Regarding Loose Breaker Control Power Fuse Caused the 3B Emergency Containment Cooler to Be Inoperable Longer than Allowed 05000250/LER-2015-001, Regarding Diesel Generator Start Resulting from Switchyard Protective Relay Actuation2016-01-19019 January 2016 Regarding Diesel Generator Start Resulting from Switchyard Protective Relay Actuation L-2015-217, Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation2015-08-27027 August 2015 Turkey, Unit 3 - Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2015-002, Regarding Reactor Trip Resulting from Generator Differential Lockout2015-07-13013 July 2015 Regarding Reactor Trip Resulting from Generator Differential Lockout 05000251/LER-2015-001, Regarding Automatic Auxiliary Feedwater System Actuation During a Planned Reactor Trip2015-01-29029 January 2015 Regarding Automatic Auxiliary Feedwater System Actuation During a Planned Reactor Trip 05000251/LER-2014-003, Regarding Emergency Containment Cooler Safety Function Impacted During Breaker Replacement2014-11-10010 November 2014 Regarding Emergency Containment Cooler Safety Function Impacted During Breaker Replacement 05000250/LER-2014-004, Regarding Ultimate Heat Sink Temperature Limit Exceeded Due to Environmental Conditions2014-09-18018 September 2014 Regarding Ultimate Heat Sink Temperature Limit Exceeded Due to Environmental Conditions 05000251/LER-2014-001, Regarding Incorrect Feedwater Flow Transmitter Calibration Caused RPS Channels to Be Inoperable2014-06-24024 June 2014 Regarding Incorrect Feedwater Flow Transmitter Calibration Caused RPS Channels to Be Inoperable 05000250/LER-2014-003, Regarding Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter2014-06-18018 June 2014 Regarding Manual Actuation of the Reactor Protection System Due to Failure of Group Step Counter 05000250/LER-2014-002, Regarding Reactor Coolant System Pressure Boundary Leakage at Pressurizer Heater Sleeve Attachment Weld2014-05-15015 May 2014 Regarding Reactor Coolant System Pressure Boundary Leakage at Pressurizer Heater Sleeve Attachment Weld L-2014-139, Special Report Regarding Accident Monitoring Instrumentation2014-05-14014 May 2014 Special Report Regarding Accident Monitoring Instrumentation 05000251/LER-2014-002, Regarding Automatic Actuation of the Reactor Protection System Due to Low Main Condenser Vacuum2014-04-24024 April 2014 Regarding Automatic Actuation of the Reactor Protection System Due to Low Main Condenser Vacuum 05000250/LER-2014-001, Regarding Missed Surveillance Test Resulted in a SG Pressure Instrument Channel to Be Inoperable Longer than AOT2014-03-0404 March 2014 Regarding Missed Surveillance Test Resulted in a SG Pressure Instrument Channel to Be Inoperable Longer than AOT 05000250/LER-2013-009, Regarding Loose Breaker Control Power Fuse Holder Caused 3B Jcw Pump to Be Inoperable Longer than AOT2013-11-27027 November 2013 Regarding Loose Breaker Control Power Fuse Holder Caused 3B Jcw Pump to Be Inoperable Longer than AOT 05000250/LER-2013-008, Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT2013-08-19019 August 2013 Regarding Through-Wall Leak in 3A CCW Pump Threaded Fitting Caused Pump to Be Inoperable Longer than AOT 05000250/LER-2013-007, Regarding Manual Reactor Trip Due to Generator Load Drop2013-07-0808 July 2013 Regarding Manual Reactor Trip Due to Generator Load Drop 05000251/LER-2013-002, Reactor Trip Due to Loss of Offsite Power Resulting from Generator Testing2013-06-18018 June 2013 Reactor Trip Due to Loss of Offsite Power Resulting from Generator Testing 05000251/LER-2013-001, Regarding Power Operated Relief Valve Inoperable for Greater than Allowed Outage Time Due to Lifted Leads2013-05-22022 May 2013 Regarding Power Operated Relief Valve Inoperable for Greater than Allowed Outage Time Due to Lifted Leads 05000250/LER-2013-006, Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps2013-05-13013 May 2013 Regarding Reactor Protection and Auxiliary Feed Water System Actuations Due to Trip of Operating Feed Water Pumps 05000250/LER-2013-005, Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves2013-05-10010 May 2013 Reactor Trip Due to Turbine Header Pressure Spike While Testing Turbine Control Valves 05000250/LER-2013-004, Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position2013-04-29029 April 2013 Safety Injection Flow Path Not Isolated Due to Manual Valve Out of Position 05000250/LER-2013-003, Regarding Manual Reactor Trip Due to Increasing Reactor Coolant Pump Seal Leakage2013-04-19019 April 2013 Regarding Manual Reactor Trip Due to Increasing Reactor Coolant Pump Seal Leakage 05000250/LER-2013-002, Regarding Automatic Reactor Trip Due to Low Condenser Vacuum2013-04-11011 April 2013 Regarding Automatic Reactor Trip Due to Low Condenser Vacuum 05000250/LER-2013-001, Regarding Procedure Noncompliance Causes Incorrect Instrument Setting and Condition Prohibited by Technical Specifications2013-03-0101 March 2013 Regarding Procedure Noncompliance Causes Incorrect Instrument Setting and Condition Prohibited by Technical Specifications 2024-07-10
[Table view] |
LER-2018-001, Inoperable Auxiliary Feedwater Steam Supply Flowpath |
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text
U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555-0001 Re:
Turkey Point Unit 4 Docket No. 50-251 Licensee Event Report: 2018-001-00 Date of Event: May 7, 2018 Inoperable Auxiliary Feedwater Steam Supply Flowpath JUN 2 7 2018 L-2018-127 10 CFR § 50.73 The attached Licensee Event Report 05000251/2018-001-00 is submitted pursuant to 10 CFR 50.73(a)(2)(i)(B) as a condition prohibited by the Turkey Point Unit 4 Technical Specifications.
If there are any questions, please call Mr. Robert J. Hess, Licensing Manager at 305-246-4112.
Sincerely, p..~
Brian Stamp Plant General Manager Turkey Point Nuclear Plant Attachment cc:
Regional Administrator, USNRC, Region II Senior Resident Inspector, USNRC, Turkey Point Nuclear Plant Florida Power & Light Company 9760 SW 344th St., Homestead, FL 33035
NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2018)
, the NRC may not conduct or sponsor, and a oerson is not reauired to resoond to, the information collection.
,3. Page Turkey Point Unit 4 05000251 1 OF3
- 4. Title Inoperable Auxiliary Feedwater Steam Supply Flowpath
- 5. Event Date
- 6. LER Number
- 7. Report Date
- 8. Other Facilities Involved Sequential Rev Facility Name Docket Number Month Day Year Year Month Day Year Number No.
05000 05 07 2018 2018
- - 001 06 27 2018 Facility Name Docket Number
- - 0 05000 Abstract (Limit to 1400 spaces, i.e., approximately 14 single-spaced typewritten lines)
On May 7, 2018 at 0049 while operating in Mode 1 at 100% power, Turkey Point Unit 4 experienced a failure of the steam generator A auxiliary feedwater (AFW) steam supply valve during preplanned surveillance testing. A review of the failure identified that it likely existed since the prior surveillance test on April 11, 2018. The resulting inoperability period of 26 days exceeded the seven-day allowed out of service time for an inoperable steam supply flowpath in Turkey Point Unit 4 Technical Specification (TS) 3.7.1.2, Auxiliary Feedwater System, resulting in a condition prohibited by TS. No adverse consequences resulted from this event.
The cause of the failure of the steam supply valve was disengagement of the torque arm from the stem key. With the torque arm disengaged from the key, the valve stem rotated and caused the geared limit switch settings for the motor operator to become out of sync with the valve travel. As a result, the limit switches did not actuate at the expected set points. Corrective actions included repairing the torque arm, overhauling the motor-operator, resetting the limit switches, installing a set screw as a secondary restraint on the torque arm, and revising maintenance procedures to verify position and tightness of the torque arm or anti-rotation device during preventative maintenance activities.
NRG FORM 366 (04-2018)
Description of Event
SEQUENTIAL NUMBER
- - 001 REV NO.
- - 0 On May 7, 2018 at 0049 while operating in Mode 1 at 100% power, Turkey Point Unit 4 experienced a failure of the steam generator (SG) [SG] A auxiliary feedwater (AFW) steam supply valve [BA, 20] during preplanned surveillance testing. A review of the failure identified that it likely existed since the prior surveillance test on April 11, 2018. The resulting inoperability period of 26 days exceeded the seven-day allowed out of service time for an inoperable steam supply flowpath in Turkey Point Unit 4 Technical Specification (TS) 3.7.1.2, Auxiliary Feedwater System, resulting in a condition prohibited by TS.
Cause of the Event
The direct cause of the event was that the torque arm on MOV-4-1403, SG-A AFW steam supply valve, was disengaged from the stem key. With the torque arm disengaged from the key, the valve stem rotated causing the geared limit switch [BA, ZIS] settings for the motor operator to become out of sync with the valve travel. The most likely cause of the torque arm being loose was that preventive maintenance procedures did not include steps to verify the torque arm is properly positioned and correctly tightened on the valve stem.
Analysis of Event
The AFW system includes three steam turbine-driven pumps [BA, P] for Turkey Point Units 3 and 4. The three pumps are installed such that each pump supplies AFW to either Unit 3 or 4, with any single pump supplying the total feedwater requirement of either unit. Two pumps are normally aligned to AFW Train 2 and the third pump is normally aligned to AFW Train 1. Upon initiation of the AFW system, the turbine steam supply isolation valves automatically open and actuate position switches, which in turn actuate opening of the AFW flow control valves [BA, FCV].
During surveillance testing on May 7, 2018, the limit switches associated with MOV-4-1403, SG-A AFW steam supply valve, did not actuate as required when the valve was opened. As a result, the AFW flow control valves did not open automatically.
Troubleshooting found the MOV-4-1403 torque arm (anti-rotation device) out of position and disengaged from the stem key. With the torque arm disengaged from the key, the valve stem was able to rotate causing the geared limit switch settings on the motor operator to become out of sync with the valve travel. As a result, the limit switches did not actuate at the expected set points.
Investigation determined that the limit switch misalignment occurred during surveillance testing on April 11, 2018 when the valve was last closed. Technical Specification (TS) 3.7.1.2, Auxiliary Feedwater System, allows seven days to restore an inoperable steam supply flow path to operable status. Since the flow path was inoperable for approximately 26 days, this event is reportable in accordance with 10 CFR 50. 73(a)(2)(i)(B) as a condition prohibited by the TS.
Turkey Point TS 3.7.1.2 requires two independent AFW trains with three steam supply flow paths and three pumps to be operable in Modes 1, 2 and 3. With the single AFW steam supply flow inoperable, two redundant flow paths were available to support operation of the AFW system. Therefore, this event did not involve a safety system functional failure. No adverse consequences resulted from this event, and the event had no adverse impact on the health and safety of the public or the plant and its personnel.
NRG FORM 3668 (02-2018)
Page 2 of 3 (04-2018)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 3. LERNUMBER YEAR Turkey Point Unit 4 05000-251 2018
Corrective Actions
SEQUENTIAL NUMBER
- - 001 REV NO.
- - 0 Corrective actions to repair the torque arm, overhaul the motor-operator, and reset the limit switches during static diagnostic testing were completed on AFW steam supply valve MOV-4-1403. Additionally, the torque arm key was replaced and a modification was implemented to install a set screw as a secondary restraint on the torque arm.
Corrective actions are planned to revise maintenance procedures to verify the position and tightness of the torque arm or anti-rotation device during preventative maintenance activities.
Actions to address extent of condition verified that the torque arm and valve stem key of the remaining AFW valves susceptible to the same condition were properly positioned and tighten. Additionally, set screws were installed in the AFW steam supply valve torque arms as a secondary restraint on the torque arm.
Additional Information
The Energy Industry Identification System (EIIS) codes are included in this LER in the following format: [EIIS system identifier, Ells component identifier].
Turkey Point Condition Report AR 2262955.
Similar Events
A review of the LERs issued over the last five years related to the AFW system revealed no similar occurrences at Turkey Point. Page 3 of 3