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Category:Letter
MONTHYEARML25073A0452025-03-13013 March 2025 Ametek Sci - Notification of Potential Defect - 10CFR Part 21 IR 05000390/20240062025-03-11011 March 2025 Annual Assessment Letter for Watts Bar Nuclear Plant, Units 1 and 2 Report 05000390/2024006 and 05000391/2024006 IR 05000390/20253012025-03-11011 March 2025 Notification of Licensed Operator Retake Examination 05000390/2025301 and 05000391/2025301 IR 05000390/20254202025-03-0404 March 2025 Security Baseline Inspection Report 05000390/2025420 and 05000391/2025420 CNL-25-036, Correction to Organization Topical Report, TVA-NPOD89-A, Revision 262025-03-0303 March 2025 Correction to Organization Topical Report, TVA-NPOD89-A, Revision 26 05000390/LER-2025-001, Loss of the Control Room Emerency Air Temperature Control System Due to Chiller Oil Migration2025-03-0303 March 2025 Loss of the Control Room Emerency Air Temperature Control System Due to Chiller Oil Migration ML25052A0882025-02-27027 February 2025 Regulatory Audit Plan in Support of License Amendment Request to Use Online Monitoring Methodology ML25051A1762025-02-26026 February 2025 Regulatory Audit Plan in Support of License Amendment Request to Adopt Risk-Informed Completion Times CNL-25-010, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Response to Request for Additional Information - TVA Request for Approval of Revision 43 to TVA Fleet Quality Assurance Program Description2025-02-26026 February 2025 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Response to Request for Additional Information - TVA Request for Approval of Revision 43 to TVA Fleet Quality Assurance Program Description ML25050A0422025-02-14014 February 2025 57484-EN 57484 - Final Report Notification Pursuant to 10 CFR 21.21 Regarding Limitorque SMB-00 Torque Switch Assemblies IR 05000390/20240042025-02-13013 February 2025 Integrated Inspection Report 05000390/2024004 and 05000391/2024004 and Apparent Violation CNL-25-028, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for (SQN-TS-23-02 & WBN-TS-23-08) (EPID L-2023-LLA-01752025-02-12012 February 2025 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for (SQN-TS-23-02 & WBN-TS-23-08) (EPID L-2023-LLA-0175 CNL-25-026, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2025-02-12012 February 2025 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20244032025-01-31031 January 2025 Watts Barr Nuclear Plant - Material Control and Accounting Program Inspection Report 05000390/2024403 and 05000391/2024403 (Public) CNL-25-009, And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 262025-01-29029 January 2025 And Watts Bar Nuclear Plant, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A, Revision 26 05000391/LER-2025-001, Loss of the Control Room Emergency Air Temperature Control System Due to Chiller Valve Malfunction2025-01-21021 January 2025 Loss of the Control Room Emergency Air Temperature Control System Due to Chiller Valve Malfunction IR 05000390/20254022025-01-17017 January 2025 Information Request for the Cybersecurity Baseline Inspection Notification to Perform Inspection 05000390/2025402 05000391/2025402 CNL-25-012, Supplement to License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources - Operating to Clarify Requirements for Diesel Generator .2025-01-16016 January 2025 Supplement to License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources - Operating to Clarify Requirements for Diesel Generator . CNL-24-076, Response to Request for Additional Information Regarding Application to Modify the Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2025-01-16016 January 2025 Response to Request for Additional Information Regarding Application to Modify the Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000391/20240402025-01-16016 January 2025 95001 Supplemental Inspection Report 05000391/2024040 and Follow-Up Assessment Letter ML25006A1172025-01-10010 January 2025 – Review of the Fall 2023 Steam Generator Tube Inspection Report (EPID-L-2024-LRO-0022) ML24354A1582025-01-0303 January 2025 Reissue Technical Specification Pages for Amendment No. 170 to Facility Operating License No. NPF-90 CNL-25-001, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-12-27027 December 2024 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML24312A3222024-12-23023 December 2024 Issuance of Amendment Nos. 334, 357, & 317; 368 & 362; 172 & 77 Regarding Revision to TS 5.4 & 5.7.1 ML24312A0052024-12-23023 December 2024 Issuance of Amendment No. 171 Regarding Extension of Facility Operating License Expiration Date to Recapture Low-Power Operating License Testing Time CNL-24-009, Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations2024-12-17017 December 2024 Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations ML24285A2072024-12-17017 December 2024 Amendment Nos. 170 and 76 Regarding the Revision of Technical Specifications 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, and 5.9.5 by Adopting Various Technical Specifications Task Force Travelers CNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML24346A3982024-12-16016 December 2024 NRC Examination Results Summary Examination Report 05000390/2024301 and 05000391/2024301 ML24352A0092024-12-16016 December 2024 Investigation Summary, Office of Investigations Case Number 2-2023-007 IR 05000390/20243012024-12-16016 December 2024 NRC Operator License Examination Report 05000390/2024301 and 05000391/2024301 CNL-24-072, Request for Alternative to Extend First Containment Inservice Inspection Interval2024-12-12012 December 2024 Request for Alternative to Extend First Containment Inservice Inspection Interval CNL-24-075, Response to Request for Additional Information for Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah and Watts Bar (SQN-TSTS-23-02 and W2024-11-27027 November 2024 Response to Request for Additional Information for Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah and Watts Bar (SQN-TSTS-23-02 and WBN ML24297A4632024-11-21021 November 2024 – Environmental Assessment and Finding of No Significant Impact Related to Recapture of Low-Power Testing Time CNL-24-080, Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011)2024-11-20020 November 2024 Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (WBN-19-011) IR 05000390/20240032024-11-13013 November 2024 Integrated Inspection Report 05000390/2024003, 05000391/2024003 & 07201048/2024001 CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) CNL-24-064, Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R52024-11-0404 November 2024 Response to Request for Additional Information Regarding the Watts Bar Nuclear Plant, Unit 2 Steam Generator Tube Inspection Report for U2R5 IR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24290A1202024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2025-03-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000390/LER-2025-001, Loss of the Control Room Emerency Air Temperature Control System Due to Chiller Oil Migration2025-03-0303 March 2025 Loss of the Control Room Emerency Air Temperature Control System Due to Chiller Oil Migration 05000391/LER-2025-001, Loss of the Control Room Emergency Air Temperature Control System Due to Chiller Valve Malfunction2025-01-21021 January 2025 Loss of the Control Room Emergency Air Temperature Control System Due to Chiller Valve Malfunction 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation 05000391/LER-2023-003-01, Automatic Reactor Trip Due to Loss of Main Feedwater Regulating Valve Control2024-02-29029 February 2024 Automatic Reactor Trip Due to Loss of Main Feedwater Regulating Valve Control 05000391/LER-2023-003, Automatic Reactor Trip Due to Loss of Main Feedwater Regulating Valve Control2023-10-0303 October 2023 Automatic Reactor Trip Due to Loss of Main Feedwater Regulating Valve Control 05000390/LER-2023-001-01, Inadequate 10 CFR 50.59 Results in Failure to Obtain Prior NRC Approval for Condition Prohibited by Technical Specifications2023-09-27027 September 2023 Inadequate 10 CFR 50.59 Results in Failure to Obtain Prior NRC Approval for Condition Prohibited by Technical Specifications 05000391/LER-2023-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2023-08-24024 August 2023 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation 05000391/LER-2023-001, Unanalyzed Condition Related to Loss of the 2A Emergency Diesel Generator During a Postulated Appendix R Fire2023-07-20020 July 2023 Unanalyzed Condition Related to Loss of the 2A Emergency Diesel Generator During a Postulated Appendix R Fire 05000390/LER-2023-001, Interpretation of Technical Specification (TS) Table 1.1-1 Leads to a Condition Prohibited by TS2023-07-0303 July 2023 Interpretation of Technical Specification (TS) Table 1.1-1 Leads to a Condition Prohibited by TS 05000391/LER-2021-001, Automatic Reactor Trip on Main Turbine Trip Caused by Main Feed Pump Trip Due to Low Condenser Vacuum2021-05-10010 May 2021 Automatic Reactor Trip on Main Turbine Trip Caused by Main Feed Pump Trip Due to Low Condenser Vacuum 05000390/LER-2021-001, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open2021-04-20020 April 2021 Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open 05000391/LER-2020-004, Steam Generators Degraded Due to Axial Outside Diameter Stress Corrosion Cracking2021-01-0707 January 2021 Steam Generators Degraded Due to Axial Outside Diameter Stress Corrosion Cracking 05000390/LER-2020-005, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 2A-A Shutdown Board2021-01-0404 January 2021 Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 2A-A Shutdown Board 05000391/LER-2020-003, Re Low RHR Flow in Mode 6 Results in a Condition Prohibited by Technical Specifications2020-12-21021 December 2020 Re Low RHR Flow in Mode 6 Results in a Condition Prohibited by Technical Specifications 05000391/LER-2020-002, Re Two Pressurizer Safety Valves Outside of Technical Specification Limits Due to Set Point Drift2020-12-17017 December 2020 Re Two Pressurizer Safety Valves Outside of Technical Specification Limits Due to Set Point Drift 05000390/LER-2020-003, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open2020-09-10010 September 2020 Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open 05000391/LER-2020-001, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open2020-07-15015 July 2020 Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open 05000390/LER-2020-002, Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board2020-07-14014 July 2020 Automatic Start of the Emergency Diesel Generators Due to an Equipment Failure During Transfer of Power Source for the 1B-B Shutdown Board 05000390/LER-2020-001, Manual Reactor Trip Due to Lowering Steam Generator Level Caused by a Hand Station Failure2020-04-17017 April 2020 Manual Reactor Trip Due to Lowering Steam Generator Level Caused by a Hand Station Failure 05000390/LER-2019-004, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open2020-01-13013 January 2020 Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open 05000390/LER-2019-003, Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed2019-10-21021 October 2019 Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed 05000391/LER-2019-002, Breach Due to Penetration Boot Seal Separation Results in Shield Building Inoperability2019-08-19019 August 2019 Breach Due to Penetration Boot Seal Separation Results in Shield Building Inoperability 05000390/LER-2019-002, Loss of Control Room Emergency Air Temperature Control System Due to Air Filter Failure2019-08-0707 August 2019 Loss of Control Room Emergency Air Temperature Control System Due to Air Filter Failure 05000391/LER-2019-001, Regarding Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed2019-07-18018 July 2019 Regarding Manual Reactor Trip Due to Main Feedwater Regulating Valve Failing Closed 05000390/LER-2018-006, Containment Air Return Fan Inoperable for a Time Period Longer than Allowed by Technical Specifications Due to an Inadequate Post Maintenance Test2019-02-11011 February 2019 Containment Air Return Fan Inoperable for a Time Period Longer than Allowed by Technical Specifications Due to an Inadequate Post Maintenance Test 05000390/LER-2018-005, Regarding Manual Reactor Trip Due to Failure of Reactor Coolant Pump to Transfer to Normal Power2018-12-19019 December 2018 Regarding Manual Reactor Trip Due to Failure of Reactor Coolant Pump to Transfer to Normal Power 05000390/LER-2018-004, Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open2018-11-13013 November 2018 Control Room Emergency Ventilation System Inoperable Due to Main Control Room Door Being Left Open 05000391/LER-2018-005, For Watts Bar Nuclear Plant, Unit 2, Automatic Reactor Trip Due to Turbine Control System Card Failure and Throttle Valve Closure2018-10-22022 October 2018 For Watts Bar Nuclear Plant, Unit 2, Automatic Reactor Trip Due to Turbine Control System Card Failure and Throttle Valve Closure 05000391/LER-2018-004, Failure to Implement Annunciator Response Process Results in a Condition Prohibited by Technical Specifications2018-09-21021 September 2018 Failure to Implement Annunciator Response Process Results in a Condition Prohibited by Technical Specifications 05000391/LER-2018-003, Reactor Trip Due to Main Generator Differential Relay Actuation2018-08-21021 August 2018 Reactor Trip Due to Main Generator Differential Relay Actuation 05000391/LER-2018-002, Loss of Shield Building Vacuum Due to Equipment Failure2018-07-0909 July 2018 Loss of Shield Building Vacuum Due to Equipment Failure 05000390/LER-2018-002-01, Shield Building Inoperability Due to Annulus Vacuum Transient2018-06-26026 June 2018 Shield Building Inoperability Due to Annulus Vacuum Transient ML18144A9982018-05-24024 May 2018 Ventilation System Inoperable Due to Main Control Room Door Being Left Open 05000390/LER-2018-002, Regarding Shield Building Inoperability Due to Annulus Vacuum Transient2018-03-19019 March 2018 Regarding Shield Building Inoperability Due to Annulus Vacuum Transient 05000390/LER-2017-016, Regarding System Actuations Due to Opening of Feeder Breaker to the 1B-B 6.9 Kv Shutdown Board2018-02-20020 February 2018 Regarding System Actuations Due to Opening of Feeder Breaker to the 1B-B 6.9 Kv Shutdown Board 05000391/LER-2017-006, Regarding Manual Reactor Trip in Response to Indication of Multiple Dropped Control Rods2018-02-0909 February 2018 Regarding Manual Reactor Trip in Response to Indication of Multiple Dropped Control Rods 05000391/LER-1917-005, Regarding Unplanned Emergency Core Cooling System Injection Into the Reactor Coolant System Due to Personnel Error2018-01-25025 January 2018 Regarding Unplanned Emergency Core Cooling System Injection Into the Reactor Coolant System Due to Personnel Error 05000390/LER-1917-015, Regarding Failure to Enter Limiting Condition of Operation Action Statement Results in a Condition Prohibited by Technical Specifications2018-01-0808 January 2018 Regarding Failure to Enter Limiting Condition of Operation Action Statement Results in a Condition Prohibited by Technical Specifications 05000390/LER-1917-014, Regarding Main Control Room Boundary Door Left Open Leading to a Loss of Safety Function2017-12-20020 December 2017 Regarding Main Control Room Boundary Door Left Open Leading to a Loss of Safety Function 05000390/LER-1917-013, Regarding Incorrectly Adjusted Auxiliary Building Gas Treatment System Damper Leads to a Condition Prohibited by Technical Specifications2017-11-0606 November 2017 Regarding Incorrectly Adjusted Auxiliary Building Gas Treatment System Damper Leads to a Condition Prohibited by Technical Specifications 05000390/LER-1917-012, Regarding Error in Plant Emergency Procedures Leads to a Condition Prohibited by the Technical Specifications2017-10-23023 October 2017 Regarding Error in Plant Emergency Procedures Leads to a Condition Prohibited by the Technical Specifications 05000390/LER-1917-011, Regarding Failure to Enter Technical Specification 3.6.3 for Containment Lsolation Valve2017-10-23023 October 2017 Regarding Failure to Enter Technical Specification 3.6.3 for Containment Lsolation Valve 05000390/LER-1917-010, Regarding Actuation of Turbine Driven Auxiliary Feedwater Pump Due to Loss of 6.9kV Shutdown Board2017-10-10010 October 2017 Regarding Actuation of Turbine Driven Auxiliary Feedwater Pump Due to Loss of 6.9kV Shutdown Board 05000391/LER-1917-004, Regarding Manual Reactor Trip Due to Inoperable Rod Position Indication2017-09-25025 September 2017 Regarding Manual Reactor Trip Due to Inoperable Rod Position Indication 05000390/LER-1917-008, Regarding Shield Building Inoperability and Potential Loss of Safety Function Resulting from Spurious Equipment Operation2017-08-14014 August 2017 Regarding Shield Building Inoperability and Potential Loss of Safety Function Resulting from Spurious Equipment Operation 05000390/LER-1917-007, Regarding Multiple Unreported Potential Loss of Safety Function Events Associated with Inoperable Single Train Systems Due to Misinterpretation of Reporting Guidance2017-08-0808 August 2017 Regarding Multiple Unreported Potential Loss of Safety Function Events Associated with Inoperable Single Train Systems Due to Misinterpretation of Reporting Guidance 05000390/LER-1917-006, Regarding Structural Degradation of 161 Kv Line Pole Leads to a Condition Prohibited by Technical Specifications2017-07-31031 July 2017 Regarding Structural Degradation of 161 Kv Line Pole Leads to a Condition Prohibited by Technical Specifications 2025-03-03
[Table view] |
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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381 June 30, 2016 10 cFR 50 73 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-000 1 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Licensee Event Report 390/2016-006-00, Undersized Room Cooler Fan Shaft Results in Loss of Centrifugal Charging Pump This submittal provides Licensee Event Report (LER) 390/2016-006-00. This LER provides details concerning maintenance performed on a safety related room cooler which resulted in a reportable condition. This report is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B) and 10 cFR 50.73(a)(2)(vXD).
Please direct any questions concerning this matter to Gordon Arent, WBN Licensing Director, at (423) 365-2004.
Respectfully, Pau! Simmons Site Vice President Watts Bar Nuclear Plant Enclosure cc: See Pag e 2
U.S. Nuclear Regulatory Commission Page 2 June 30, 2016 cc (Enclosure):
NRC Regional Administrator - Region ll NRC Senior Resident lnspector - Watts Bar Nuclear Plant
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (1 1-201s) a.f'"*ur:o, iWi
"^--G,r"f, LIGENSEE EVENT REPORT (LER) n aa.,,
APPROVED BY OMB: NO.3150-0104 EXPIRES: 10/31/20{8
, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.
- 1. FACILIW NAME Watts Bar Nuclear Plant, Unit 1
- 2. DOCKET NUMBER 05000390
- 3. PAGE 1
OF 6
- 4. TITLE Undersized Room Cooler Fan Shaft Results in Loss of Centrifugal Charging Pump
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTHI DAY I YEAR YEAR I t=-t'^F$ft REV NO.
MONTH I DAY YEAR FACILIry NAME I
DOCKET NUMBER N/A ln'rn 05 13 I 2016 2016 -006
- - 00 06 30 2016 FACILITY NAME I
DOCKET NUMBER N/A lN/A
- 9. OPERATING MODE II.THISREPORTISSUBMITTEDPURSUANTTOTHEREQUIREIIENTSOFI0CFRg: (CDeckailthatapply) 1 tr 20.2201(b) n 2o.zzos(aX3Xi) tr 50.73(aX2XiiXA) tr 50.73(aX2Xv.i.XA) tr 2o.zzo1(d) n 2o.z2o3(aX3Xii) tr 50.73(a)(2XiiXB) tr 50.73(a)(2)(viii)(B) tr zo,zzo3(aX1) tr zo 22o3(aX4) tr 50.73(ax2xiii) tr s0.73(a)(2)(ix)(A) tr 20.2203(aX2Xi) tr 50.36(cX1X.XA) tr 50.73(aX2Xiv)(A) tr 50.73(aX2)(x)
- 10. POWER LEVEL 100 tr 20.2203(a)(2)(i.)
tr s0.36(c)(l XiiXA) tl s0.73(a)(2)(vXA) tr rc.l'.(aX4) tr 2o.z2os(a)(2)(iii) tr s0.36(cX2) tr 50.73(ax2)(vXB) tr rcl1(a)(s) tr 2o.z2o3(aX2Xiv) n 50.46(ax3xii) tr 50.73(aX2XvXc) tr rc,Tl(a)(1) tr 2o.2zo3(aX2Xv) n 50.73(a)(2)(i)(A)
X s0.73(aX2Xv)(D) tr ftll(ax2xi) tr 2o.z2o3(aX2Xvi)
X 50.73(aX2XiXB) tr s0.73(a)(2)(vii) tr ftll(ax2xii) n 50.73(aX2XiXc) tr OTHER Specify in Abstract betow or in Date Time (EST) Event 1126116 A past operability evaluation associated with the 1B-B CCP room cooler determines the fan was operable up until failure.
3/06/16 CR 1146474 generated to perform an equipment apparent cause evaluation (EACE) on the 1B-B CCP room cooler failure.
4121116 CR 1146474 EACE Approved 5113116 CR 1165380 determines this issue to be reportable to NRC.
6123116 Past Operability Evaluation associated with the 1B-B CCP and 1A-A CCP approved.
D. Manufacturer and Model Number of Components that Failed Ellis & Watts fan cooler, Model ACH101.
E. Other Systems or Secondary Functions Affected
Other than the 1B-B CCP and 1A-A CCP, no other systems or functions were affected.
F. Method of discovery of each Component or System Failure or Procedural Error
The immediate failure of the fan was discovered during operations tours.
G. Failure Mode and Effect of Each Failed Component The cause of the fan bearing failure was an undersized fan shaft, resulting in the 1B-B CCP fan having excess shaft to bearing clearance which caused the bearing inner ring to loosen from the eccentric locking collar. These excessive clearances allowed the fan bearing inner ring to slide on the shaft. The sliding rotation of the inner ring on the shaft resulted in excessive heat being generated within the bearing leading to catastrophic failure.
H. Operator Actions
Upon identifying the failure of the 1B-B CCP room cooler on December 4,2015, the Technical Specification Limiting Condition of Operation (LCO) 3.5.2 was entered for the 1B-B CCP.
l. Automatically and Manually lnitiated Safe$ System Responses There were no automatic or manual safety systems responses required. Upon declaring the 1B-B CCP inoperable, the 1A-A CCP was placed in service.
III. CAUSE OF THE EVENT
A. The cause of each component or system failure or personnel error, if known.
The cause of the fan bearing failure was an undersized fan shaft, resulting in the 1B-B CCP fan having excess shaft to bearing clearance which caused the bearing inner ring to loosen from the eccentric locking collar. These excessive clearances allowed the fan bearing inner ring to slide on
IV the shaft. The sliding rotation of the inner ring on the shaft resulted in excessive heat being generated within the bearing leading to catastrophic failure. During maintenance on the 1B-B CCP room cooler, procedures associated with the bearing replacement did not confirm the fan shaft size to be outside design specifications.
The cause(s) and circumstances for each human performance related root cause.
There were no human performance causes associated with this failure.
ANALYSIS OF THE EVENT
On December 4,2015 at 1042, WBN personnel discovered the 1 B-B CCP room cooler with belts thrown and not cooling. The reason the belts were thrown was discovered to be failure of the outboard flange bearing on the fan shaft of the cooler. Preventative maintenance was performed on the fan unit during the WBN Unit 1 outage on September 27,2015 and returned to service on October 7,2015. At the time the preventative maintenance was performed in October 2015, workers discovered that the remote grease fitting line to the flange of the bearing assembly was missing. This grease line was not restored prior to the fan being returned to service.
The fan failure on December 4,2015 was documented in Condition Report (CR) 11'11791, and the fan was repaired and returned to service on December 6, 2015. The evaluation performed by CR 1111791 addressed this issue as a human performance event because of the missing grease line. Subsequently, in the past operability evaluation for CR 1111791, WBN concluded that, based on interactions with the bearing manufacturer, the cause of the bearing failure was not the broken grease line.
ln order to determine the cause of the bearing failure and to support a determination of reportability, WBN generated CR 1146474 to perform an equipment apparent cause evaluation (EACE) associated with the 1B-B CCP room cooler fan failure. This EACE determined that the cause of the fan bearing failure was an undersized fan shaft.
The CCPs are a component of the Emergency Core Cooling System (ECCSXEIIS:BQ), providing high head injection into the Reactor Coolant System (RCS). The Specified Safety Function of the ECCS is to cool the reactor core as well as to provide additional shutdown capability following initiation of an accident.
The specified mission time for the CCPs is 100 days. Because the fan had an undersized shaft, the room cooler fan was unable to support the mission time of the 1B-B CCP following an accident. Based on the results of the EACE, the installed fan had a mechanical condition that impacted the fans specified safety function. The room cooler fan was determined to be inoperable from the date of its return to service on October 7,2015 until it was repaired on December 6, 2015. Accordingly, the associated CCP is considered to be inoperable for the same time period.
During the period of inoperability of the 1B-B CCP (October 7 through December 6, 2015), the 1A-A CCP remained operable except for four specific limited time intervals. On November 11 and 12,2015, the 1A-A CCP experienced low CCS flow to its associated bearing and gear oil coolers for time periods of 2 minutes, 1 minute and 9 minutes. lf proceduralized operator actions had not been taken to restore adequate flow, the pumps could have failed to perform their specified functions. ln addition, on November 12,2015, with the 1B-B CCP in service, the 1A-A CCP was inoperable due to being placed in pull-to-lock for the cold overpressure mitigation system (COMS) in preparation for entry into Mode 4. lf an accident
had occurred at this time, without operator action to restore the 1A-A CCP, a loss of the 1B-B CCP would be expected to occur prior to completing its mission time.
A risk review was performed related to this condition. While the 1B-B CCP was inoperable, it was available to perform its safety function. The risk review shows that with an unavailability of five days during this period, the core damage frequency associated with the 1B-B CCP remained below 'tE-6.
V. ASSESSMENT OF SAFETY CONSEQUENCES
A. Availability of systems or components that could have performed the same function as the components and systems that failed during the event The 1A-A CCP and associated room cooler remained operable except for four short time periods during the period between October 7,2015 and December 6, 2015. During the time periods of low flow the 1A-A CCP, while not operable, was available. Considering operator responses to restore adequate CCS flow to the 1A-A CCP, there is confidence that the 1A-A CCP would have been able to perform its function had an accident occurred.
During the time period when the 1A-A CCP was in a pull-to-lock status for COMS, the plant was in a condition authorized by TS which limited operability of the charging system to one pump. ln the event of an accident, it is reasonable to conclude that operator action would have been taken to start the 1A-A CCP if required.
B. For events that occurred when the reactor was shut down, availability of systems or components needed to shutdown the reactor and maintain safe shutdown conditions, remove residual heat, control the release of radioactive material, or mitigate the consequences of an accident Not applicable.
C. For failure that rendered a train of a safety system inoperable, an estimate of the elapsed time from the discovery of the failure until the train was returned to service Based on review of the time that cooling stopped, and a calculation performed to estimate the time of the bearing failure, the total time that the fan for the 1B-B CCP was not available was from December 4,2015 at 0300 until December 6, 201 5 at 0322, or 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and 22 minutes.
VI. CORRECTIVE ACTIONS
This event was entered into the Tennessee Valley Authority (TVA) Corrective Action Program and is being tracked under CRs 1111791, 1146474, 1 165380, and 1177072.
A. lmmediate Corrective Actions The failed CCP room cooler was repaired and returned to service.
B. Corrective Actions to Prevent Recurrence The procedure governing maintenance of belt driven equipment will be revised to explicitly measure shaft size and validate against design requirements. The tensioning requirements for belt driven equipment will also be revised such that the lowest tension will be used that does not result in belt slipping.
VII. ADDITIONAL INFORMATION
A. Previous similar events at the same plant On November 3, 1995, WBN Unit 1 reported a construction deficiency related to cooler fan shaft damage under 10 CFR 50.55(e). A final report was provided by TVA on December 4, 1995. The cause of the fan shaft damage was over tensioning of the fan belts. Contributing causes were (1) loose bearing to shaft fit, (2) improper alignment of shafts, (3) flexible bearing support mounts, and (4) shaft materialsusceptible to deflection and grooving with harder materials.
B. Additional lnformation None.
C. Safety System Functional Failure Consideration A safety system functional failure was present during the time periods when both the 1B-B CCP was inoperable and when the 1A-A CCP was inoperable for the short time periods identified.
When considering reasonable and proceduralized operator actions associated with the 1A-A CCP, however, there is confidence that the safety system function would not have been lost in the event of an accident.
D. Scrams with Complications Consideration There was no scram associated with this event.
VIII. COMMITMENTS
None.Paqe 6 of 6
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