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Category:Letter
MONTHYEARIR 05000382/20240102024-12-0606 December 2024 – Biennial Problem Identification and Resolution Inspection Report 05000382/2024010 ML24338A0522024-12-0303 December 2024 Entergy - 2024 Certification of Foreign Ownership and Control or Influence (FOCI) IR 05000382/20240122024-11-21021 November 2024 License Renewal Phase 2 Inspection Report 05000382/2024012 IR 05000382/20240032024-11-0808 November 2024 Integrated Inspection Report 05000382/2024003 ML24289A0312024-11-0808 November 2024 – Issuance of Amendments Related to the Removal of License Condition 2.F as Part of the Consolidated Line-Item Improvement Process (CLIIP) 05000382/LER-2024-001-01, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-11-0707 November 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure IR 05000382/20244022024-10-10010 October 2024 Security Baseline Inspection Report 05000382/2024402 Public IR 05000382/20244032024-10-0909 October 2024 Security Baseline Inspection Report 05000382/2024403 IR 05000382/20240112024-10-0101 October 2024 State Fire Protection Team Inspection Report 05000382/2024011 IR 05000382/20230042024-09-27027 September 2024 Amended Integrated Inspection Report 05000382/2023004 ML24229A1042024-09-25025 September 2024 Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised ML24268A1132024-09-24024 September 2024 Acknowledgment of Response to NRC Inspection Report 05000382/2024013, and Notice of Violation ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000382/20240052024-08-21021 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005 IR 05000382/20240132024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML24228A2612024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024 Automatic Reactor Trip Due to Lightning Strike IR 05000382/20240022024-08-0808 August 2024 Integrated Inspection Report 05000382/2024002 ML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24213A1632024-08-0101 August 2024 2024 Waterford Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification 05000382/LER-2024-003, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024 Automatic EFAS Actuation During Surveillance Test ML24150A3852024-06-0404 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24141A1012024-05-20020 May 2024 Amended Integrated Inspection Report 05000382/2023004 05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer Failure2024-05-16016 May 2024 Automatic Reactor Trip Due to Transformer Failure 05000382/LER-2024-001, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000382/20240012024-05-0606 May 2024 Integrated Inspection Report 05000382/2024001 ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams IR 05000382/20244012024-03-18018 March 2024 Material Control and Accounting Program Inspection Report 05000382/2024401 ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A3742024-03-15015 March 2024 Acknowledgement of Response to NRC Inspection Report 05000382/2023004 and Disputed Non-Cited Violation ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24032A0032024-03-0606 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0053 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000382/20230062024-02-28028 February 2024 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006 05000382/LER-2023-004, Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement2024-02-14014 February 2024 Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement ML24039A1992024-02-12012 February 2024 – Integrated Inspection Report 05000382/2023004 IR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and 05000382/LER-2023-003, Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing2023-12-30030 December 2023 Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment 2024-09-06
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000382/LER-2024-001-01, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-11-0707 November 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure 05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024 Automatic Reactor Trip Due to Lightning Strike 05000382/LER-2024-003, Automatic EFAS Actuation During Surveillance Test2024-07-10010 July 2024 Automatic EFAS Actuation During Surveillance Test 05000382/LER-2024-002, Automatic Reactor Trip Due to Transformer Failure2024-05-16016 May 2024 Automatic Reactor Trip Due to Transformer Failure 05000382/LER-2024-001, Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure2024-05-15015 May 2024 Manual Reactor Trip Due to Engineered Safety Features Actuation System Relay Failure 05000382/LER-2023-004, Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement2024-02-14014 February 2024 Non-Compliance with Technical Specifications Due to Performing Startup Channel 1 Functional Testing During Fuel Movement 05000382/LER-2023-003, Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing2023-12-30030 December 2023 Steam Generator Tube Degradation Indicated by Failed In-Situ Pressure Testing 05000382/LER-2023-002, Plant Shutdown Required by Technical Specifications for Unidentified Reactor Coolant System Leakage in Containment2023-05-0909 May 2023 Plant Shutdown Required by Technical Specifications for Unidentified Reactor Coolant System Leakage in Containment 05000382/LER-2023-001, Non-Compliance with Technical Specifications Due to pico-ammeter Circuit Board Fluctuations in Containment High Range Radiation Monitor B2023-05-0101 May 2023 Non-Compliance with Technical Specifications Due to pico-ammeter Circuit Board Fluctuations in Containment High Range Radiation Monitor B 05000382/LER-2022-001-02, Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors2023-02-22022 February 2023 Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors 05000382/LER-2022-001-01, On Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors2023-01-0303 January 2023 On Non-Compliance with Technical Specifications Due to Incorrect Procedural Guidance for Radiation Monitors 05000382/LER-2022-006, Non-Compliance with Technical Specifications Due to Incorrect Conversion Factors in Plant Stack and Fuel Handling Building Radiation Monitors2022-11-0707 November 2022 Non-Compliance with Technical Specifications Due to Incorrect Conversion Factors in Plant Stack and Fuel Handling Building Radiation Monitors 05000382/LER-2022-005, Engineered Safety Features Actuation System Relay Failure Results in Reactor Trip and Emergency Feedwater Actuation2022-08-23023 August 2022 Engineered Safety Features Actuation System Relay Failure Results in Reactor Trip and Emergency Feedwater Actuation 05000382/LER-2022-004, Regarding Operation Prohibited by Technical Specifications Due to Inadequate Radiation Monitor Calibration Procedures2022-06-23023 June 2022 Regarding Operation Prohibited by Technical Specifications Due to Inadequate Radiation Monitor Calibration Procedures 05000382/LER-2022-003, Operation Prohibited by Technical Specifications Due to Radiation Monitor Calibration Error2022-06-13013 June 2022 Operation Prohibited by Technical Specifications Due to Radiation Monitor Calibration Error 05000382/LER-2022-002, Operation Prohibited by Technical Specifications Due to Personnel Error2022-05-13013 May 2022 Operation Prohibited by Technical Specifications Due to Personnel Error 05000382/LER-2022-001, Non-Compliance with Technical Specifications Due to Incorrect Conversion Factors in Three Gaseous Radiation Monitors2022-03-18018 March 2022 Non-Compliance with Technical Specifications Due to Incorrect Conversion Factors in Three Gaseous Radiation Monitors 05000382/LER-2021-003, Non-Compliance with Technical Specifications Due to Failed Ambient Pressure Input2021-12-16016 December 2021 Non-Compliance with Technical Specifications Due to Failed Ambient Pressure Input 05000382/LER-2021-002, Loss of Offsite Power Due to Hurricane Ida2021-11-22022 November 2021 Loss of Offsite Power Due to Hurricane Ida 05000382/LER-2021-001, Control Room Air Filtration Equipment Failure Resulting in a Condition Prohibited by Technical Specification 3.7.6.12021-02-22022 February 2021 Control Room Air Filtration Equipment Failure Resulting in a Condition Prohibited by Technical Specification 3.7.6.1 05000382/LER-2020-003, Procedure Deficiency for MG Set Voltage Regulator Installation Results in a Reactor Trip2020-12-30030 December 2020 Procedure Deficiency for MG Set Voltage Regulator Installation Results in a Reactor Trip 05000382/LER-2020-002, (Waterford 3), Operation or Condition Prohibited by Technical Specifications for Technical Specification 3.4.5.1 (Reactor Coolant System Leakage Detection Instrumentation) Due to Personnel2020-10-23023 October 2020 (Waterford 3), Operation or Condition Prohibited by Technical Specifications for Technical Specification 3.4.5.1 (Reactor Coolant System Leakage Detection Instrumentation) Due to Personnel. 05000382/LER-2020-001, (Waterford 3), Violation of Technical Specification 3.3.3.7.3.a (Broad Range Gas Detection) Due to Operators and Maintenance Technicians Not Performing Procedure Step as Intended2020-05-0707 May 2020 (Waterford 3), Violation of Technical Specification 3.3.3.7.3.a (Broad Range Gas Detection) Due to Operators and Maintenance Technicians Not Performing Procedure Step as Intended 05000382/LER-2019-005-01, Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules with the Main Exciter2020-04-0808 April 2020 Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules with the Main Exciter 05000382/LER-2019-007, (Waterford 3), Plant Shutdown Required by Technical Specifications Due to Charging Pump Suction Line Flaw2019-09-26026 September 2019 (Waterford 3), Plant Shutdown Required by Technical Specifications Due to Charging Pump Suction Line Flaw 05000382/LER-2019-006, (Waterford 3), Unplanned Loss of Both Trains of Broad Range Gas Monitors Results in a Condition That Could Have Prevented Fulfillment of a Safety Function2019-08-23023 August 2019 (Waterford 3), Unplanned Loss of Both Trains of Broad Range Gas Monitors Results in a Condition That Could Have Prevented Fulfillment of a Safety Function 05000382/LER-2019-005, Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules within the the Main Exciter2019-07-15015 July 2019 Automatic Reactor Scram Due to Steam Generator 1 High Level Resulting from a Main Turbine Trip and Subsequent Reactor Power Cutback Due to Failed Diode Modules within the the Main Exciter 05000382/LER-2019-003, Relevant Indications Identified in Reactor Coolant Pump 1A and 2A Suction Drain Nozzle Dissimilar Metal Welds Resulting in the Condition of the Nuclear Power Plant, Including Its Principal Safety Barriers, Being2019-03-15015 March 2019 Relevant Indications Identified in Reactor Coolant Pump 1A and 2A Suction Drain Nozzle Dissimilar Metal Welds Resulting in the Condition of the Nuclear Power Plant, Including Its Principal Safety Barriers, Being 05000382/LER-2019-002, (Waterford 3), Control Room Envelope Declared Inoperable Due to Outside Air Intake Isolation Valve Exceeding Closed Stroke Time During Inservice Testing Resulting in Event or Condition2019-02-18018 February 2019 (Waterford 3), Control Room Envelope Declared Inoperable Due to Outside Air Intake Isolation Valve Exceeding Closed Stroke Time During Inservice Testing Resulting in Event or Condition . 05000382/LER-2019-001, Past Inoperability of Effluent Accident Monitor Exceeds Allowed Outage Time Resulting in Condition Prohibited by Technical Specifications2019-02-11011 February 2019 Past Inoperability of Effluent Accident Monitor Exceeds Allowed Outage Time Resulting in Condition Prohibited by Technical Specifications 05000382/LER-2018-002, Unplanned Loss of a Train of Control Room Outside Air Intake Radiation Monitors Results in a Condition Prohibited by Technical Specifications2018-06-0707 June 2018 Unplanned Loss of a Train of Control Room Outside Air Intake Radiation Monitors Results in a Condition Prohibited by Technical Specifications 05000382/LER-2018-001, For Waterford Unit 3 Regarding Failure to Enter Limiting Condition of Operation Action Statement Due to Lack of Procedure Guidance Results in a Condition Prohibited by Technical Specifications2018-02-20020 February 2018 For Waterford Unit 3 Regarding Failure to Enter Limiting Condition of Operation Action Statement Due to Lack of Procedure Guidance Results in a Condition Prohibited by Technical Specifications 05000382/LER-1917-002, Regarding Automatic Reactor Scram Due to the Failure of Fast Bus Transfer Relays to Automatically Transfer Station Loads to Off-Site Power on a Main Generator Trip2017-09-18018 September 2017 Regarding Automatic Reactor Scram Due to the Failure of Fast Bus Transfer Relays to Automatically Transfer Station Loads to Off-Site Power on a Main Generator Trip 05000382/LER-1917-001, Regarding Both Trains of Emergency Core Cooling System Inoperable Due to Inadvertently Performing Maintenance on Train B Resulting in Event or Condition That Could Have Prevented Fulfillment of a Safety Function2017-05-0404 May 2017 Regarding Both Trains of Emergency Core Cooling System Inoperable Due to Inadvertently Performing Maintenance on Train B Resulting in Event or Condition That Could Have Prevented Fulfillment of a Safety Function 05000382/LER-2015-007-01, Both Emergency Diesel Generators Declared Inoperable2016-12-0606 December 2016 Both Emergency Diesel Generators Declared Inoperable 05000382/LER-2016-002, Regarding Both Trains of Essential Services Chilled Water Inoperable Due to Failing to Maintain Exiting Chilled Water Temperature in Specification Resulting in Event or Condition That Could Have Prevented2016-10-11011 October 2016 Regarding Both Trains of Essential Services Chilled Water Inoperable Due to Failing to Maintain Exiting Chilled Water Temperature in Specification Resulting in Event or Condition That Could Have Prevented 05000382/LER-2016-001, Regarding Incorrect Core Protection Calculator Addressable Constant Entered Because of Inadequate Procedure Resulting in a Condition Prohibited by Technical Specifications2016-09-0101 September 2016 Regarding Incorrect Core Protection Calculator Addressable Constant Entered Because of Inadequate Procedure Resulting in a Condition Prohibited by Technical Specifications 05000382/LER-2015-004-02, Regarding Inoperability of the Emergency Feedwater Actuation System, Emergency Feedwater (EFW) System, and Atmospheric Dump Valves Due to Improper Configuration of the EFW System Flow Control System2016-04-28028 April 2016 Regarding Inoperability of the Emergency Feedwater Actuation System, Emergency Feedwater (EFW) System, and Atmospheric Dump Valves Due to Improper Configuration of the EFW System Flow Control System 05000382/LER-2015-008, Regarding Automatic Reactor Trip Due to Failed Circuit Card in Control Element Assembly Calculator 22015-12-0202 December 2015 Regarding Automatic Reactor Trip Due to Failed Circuit Card in Control Element Assembly Calculator 2 05000382/LER-2015-007, Regarding Both Emergency Diesel Generators Declared Inoperable2015-10-23023 October 2015 Regarding Both Emergency Diesel Generators Declared Inoperable 05000382/LER-2015-004-01, Forwards LER 15-004-01 for Waterford 3, Regarding Emergency Feedwater System Flow Oscillations and LER 15-005-01 Regarding Manual Reactor Trip Due to Low Steam Generator Levels2015-08-21021 August 2015 Forwards LER 15-004-01 for Waterford 3, Regarding Emergency Feedwater System Flow Oscillations and LER 15-005-01 Regarding Manual Reactor Trip Due to Low Steam Generator Levels 05000382/LER-2015-006, Regarding Void Discovered in Low Pressure Safety Injection System Piping2015-08-18018 August 2015 Regarding Void Discovered in Low Pressure Safety Injection System Piping 05000382/LER-2015-005, Regarding Emergency Feedwater System Flow Oscillations and LER 15-005-00 Regarding Manual Reactor Trip Due to Low Steam Generator Levels2015-07-31031 July 2015 Regarding Emergency Feedwater System Flow Oscillations and LER 15-005-00 Regarding Manual Reactor Trip Due to Low Steam Generator Levels 05000382/LER-2014-004, Regarding Emergency Diesel Generators Rendered Inoperable by Potential Water Intrusion Into Diesel Fuel Oil Feed Tanks2014-12-18018 December 2014 Regarding Emergency Diesel Generators Rendered Inoperable by Potential Water Intrusion Into Diesel Fuel Oil Feed Tanks 05000382/LER-2014-002, Regarding Inadequate Tightening of Starting Air Filter Housing Results in Inoperable Train a Emergency Diesel Generator2014-04-29029 April 2014 Regarding Inadequate Tightening of Starting Air Filter Housing Results in Inoperable Train a Emergency Diesel Generator 05000382/LER-2014-001, Regarding Room Cooler Breaker Inoperability Causes Past Inoperability of Containment Spray System Train2014-02-14014 February 2014 Regarding Room Cooler Breaker Inoperability Causes Past Inoperability of Containment Spray System Train 05000382/LER-2013-007, Regarding Technical Specification 3.9.7 Violation, Load Over Irradiated Fuel During Dry Fuel Storage Activities2013-12-17017 December 2013 Regarding Technical Specification 3.9.7 Violation, Load Over Irradiated Fuel During Dry Fuel Storage Activities 05000382/LER-2013-006, Regarding Failure of Credited Operator for Air Operated Valve Causes Train Past Inoperability2013-10-31031 October 2013 Regarding Failure of Credited Operator for Air Operated Valve Causes Train Past Inoperability 05000382/LER-2013-005, Re Emergency Diesel Generator Inoperable Due to Room Exhaust Fan Failure2013-09-11011 September 2013 Re Emergency Diesel Generator Inoperable Due to Room Exhaust Fan Failure 05000382/LER-2013-004, Regarding Tech Spec Violation During Operation in Lower Mode with Reduced Channels of Excore Nuclear Instrumentation2013-09-0303 September 2013 Regarding Tech Spec Violation During Operation in Lower Mode with Reduced Channels of Excore Nuclear Instrumentation 2024-08-15
[Table view] |
LER-2021-001, Control Room Air Filtration Equipment Failure Resulting in a Condition Prohibited by Technical Specification 3.7.6.1 |
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text
Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-464-3786 Paul Wood Manager, Regulatory Assurance 10 CFR 50.73 W3F1-2021-0020 February 22, 2021 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Licensee Event Report (LER) 2021-001-00 Control Room Air Filtration Equipment Failure Resulting in a Condition Prohibited by Technical Specification 3.7.6.1 Waterford Steam Electric Station, Unit 3 (Waterford 3)
NRC Docket No. 50-382 Renewed Facility Operating License No. NPF-38 The enclosed report is being sent pursuant to 10 CFR 50.73.
This letter contains no new regulatory commitments.
Should you have any questions or require additional information, please contact Paul Wood, Regulatory Assurance Manager, at 504-464-3786.
Respectfully, Regulatory Assurance Manager PIW/jkb
Enclosure:
Waterford 3 Licensee Event Report 2021-001-00 cc:
NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford 3 NRC Project Manager - Waterford 3 Paul Wood Digitally signed by Paul Wood Date: 2021.02.22 06:50:26 -06'00'
Enclosure W3F1-2021-0020 Waterford 3 Licensee Event Report 2021-001-00
Abstract
On December 25, 2020 at 0537, Waterford 3 Steam Electric Station Control Room operators observed HVC-213A (Control Room Emergency Air Filtration Unit (EFU) Train A recirculation damper) out of its normal position during a control board walk down. Control Room EFU Train A was declared inoperable. During the restoration of the system, HVC-205A (Control Room EFU Train A inlet damper) failed open. HVC-205A was repaired and Control Room EFU Train A was declared operable on December 29, 2020 at 0200. During the past operability review, firm evidence was discovered that the condition observed on December 25, 2020 would have affected the operability of Control Room EFU Train A starting on December 21, 2020 at 1732, when HVC-213A initially moved from its intermediate to open position as indicated on the plant computer. Therefore, the total time Control Room EFU Train A was inoperable was 7 days, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 28 minutes, exceeding the Technical Specification 3.7.6.1 allowed outage time.
During as-found testing of the removed hydramotor from HVC-213A, the hydraulic pump/motor assembly seized causing excessive motor current. The hydramotor hydraulic pump/motor assembly was determined to be faulty.
Corrective action included restoring the system to operable status and revising the shiftly walkdown checklists to allow a means to detect these components being out of their normal position.
There were no consequences to the general safety of the public, nuclear safety, industrial safety or radiological safety. No radiological release occurred due to this event.
Plant Conditions
At the time of this event Waterford 3 Steam Electric Station (Waterford 3) was operating at 100% reactor power (Mode 1). There were no other structures, systems or components out of service that contributed to this event.
Event Description
On December 25, 2020 at 0537, while operating in Mode 1, at 100% power, Waterford 3 Control Room operators observed HVC-213A (Control Room Emergency Air Filtration (EFU) Train A recirculation damper) [VI, CDMP] out of its normal position during a control board walk down. Control Room EFU Train A was declared inoperable.
Maintenance was completed to repair HVC-213A. During the restoration of the system another damper, HVC-205A (Control Room EFU Train A inlet damper) [VI, CDMP], failed open. HVC-205A hydramotor was rebuilt and the damper function was restored on December 29, 2020 at 0200. Operations declared the Control Room EFU Train A operable. With the additional failure of HVC-205A, the total time that the unit was inoperable from time of discovery was 3 days 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and 23 minutes. During the past operability review, firm evidence was discovered that the as-found condition on December 25, 2020 would have affected the operability of control room EFU train A starting on December 21, 2020 at 1732, when HVC-213A initially moved from its intermediate to open position. Therefore, the total time Control Room EFU Train A was inoperable was 7 days 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 28 minutes, exceeding the Technical Specification (TS) 3.7.6.1 allowed outage time.
On December 21, 2020 at 1732, HVC-213A had failed to the open position as indicated on plant computer trending; however, Operations did not notice this change in position until December 25, 2020. The HVC-213A position indication was not part of the normal shiftly walkdown requirements. Upon discovering HVC-213A in the OPEN position, Operations declared the Control Room EFU Train A unit inoperable (December 25, 2020 at 0537).
Waterford 3 Technical Specification 3.7.6.1 Control Room Emergency Air Filtration System requires the control room emergency filtration trains to be operable in Modes 1, 2, 3, 4, 5, and 6 or during load movements with or over irradiated fuel assembles. Action a. specifies with one control room emergency air filtration train inoperable for reasons others than ACTION b, restore the inoperable train to OPERABLE status within 7 days.
Mechanical Maintenance performed a visual inspection and verified HVC-213A was in the OPEN position.
Troubleshooting determined that the cause was a failed hydramotor actuator for HVC-213A. The hydramotor was rebuilt and the damper function was restored on December 20, 2020 at 1751. Upon removing the tagout for this work, HVC-205A failed to the OPEN position. This damper also affects the operability of the Control Room EFU Train A unit. As a result, the Control Room EFU Train A remained inoperable. HVC-205A hydramotor was rebuilt and the damper function was restored on December 29, 2020 at 0200. Operations declared the Control Room EFU Train A operable. With the additional failure of HVC-205A, the total time the unit was inoperable from time of discovery was 3 days 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and 23 minutes (December 25, 2020 at 0537 through December 29, 2020 at 0200);
however, there is firm evidence that the as-found condition would have affected the operability of Control Room EFU Train A starting on December 21, 2020 at 1732 when HVC-213A initially went from its intermediate to open position. Therefore, the total time Control Room EFU Train A was inoperable was 7 days 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 28 minutes (December 21, 2020 at 1732 thru December 29, 2020 at 0200), exceeding TS 3.7.6.1 allowed outage time.
This condition is being reported pursuant to 10 CFR 50.73(a)(2)(i)(B), any operation which was prohibited by the plant's Technical Specifications.
Safety Assessment
Page 3 of 3 (08-2020)
U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 08/31/2023 LICENSEE EVENT REPORT (LER)
CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this form https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)
- 3. LER NUMBER Waterford Steam Electric Station, Unit 3 05000-382 YEAR SEQUENTIAL NUMBER REV NO.
2021 001 00 The Control Room Emergency Air Filtration system is modeled in the Probabilistic Risk Assessment (PRA);
however, it has low safety significance. The emergency filtration function and flow paths are not modeled in the PRA and not required for success. This failure, therefore, has a very low safety significance. There were no actual consequences to general safety of the public, nuclear safety, industrial safety and radiological safety for this event.
Event Cause(s):
During as-found testing of the removed hydramotor from HVC-213A, the hydraulic pump/motor assembly seized causing excessive motor current. The hydramotor hydraulic pump/motor assembly was determined to be faulty.
This is an Asco/Emerson (formally ITT Barton) model NH-91 hydramotor unit [VI, CDMP]. There was no initial indication of the cause of failure for HVC-205A hydramotor unit. This is an Asco/Emerson (formally ITT Barton) model NH-92 hydramotor unit [VI, CDMP].
Corrective Actions
WF3 has completed the following corrective actions:
HVC-213A and HVC-205A hydramotor actuators were rebuilt, tested, and the system was restored to operable status HVC-213A and HVC-213B were added to shiftly walkdown checklists to provide a means to detect these components being out of their normal position WF3 is tracking the following corrective actions to completion in its corrective action program:
Complete HVC-213A and HVC-205A hydramotor vendor detailed failure analysis (in-progress)
Previous Similar Events
None