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| {{#Wiki_filter:}} | | {{#Wiki_filter:TENNESSEE VALLEY 1\\14 AUTHORITY |
| | |
| | Post Office Box 2000, Decatur, Alabama 35609-2000 |
| | |
| | January 23, 2024 |
| | |
| | 10 CFR 21.21 |
| | |
| | ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 |
| | |
| | Browns Ferry Nuclear Plant, Units 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260 |
| | |
| | ==Subject:== |
| | Final Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump |
| | |
| | ==References:== |
| | Letter from TVA to NRC, Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump, dated December 1, 2023 (ML23335A072) |
| | |
| | On December 1, 2023, the Tennessee Valley Authority (TVA) submitted an interim Part 21 report regarding a defective overload relay at Browns Ferry Nuclear Plant (BFN). On October 2, 2023, a new overload relay was found to be defective during post-maintenance testing on a circuit breaker for the BFN, Unit 2, Reactor Core Isolation Cooling (RCIC) condensate pump. This QA1 part (DBC069X) had previously passed receipt inspection in April 2023 as part of a bulk order of 90 relays of this same type, of which, 82 remained in stock. This issue was promptly entered into the BFN Corrective Action Program (CAP) as Condition Report (CR) 1883872. |
| | |
| | The manufacturer, GE-Hitachi (GEH), has inspected and tested the relay. Based upon TVAs evaluation of GEHs report, BFN Engineering had concluded that this is not a Part 21 reportable issue. |
| | |
| | There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact David Renn, Site Licensing Manager, at (256) 729-2636. |
| | |
| | Respectfully, |
| | |
| | M.Sivaraman Site Vice President U.S. Nuclear Regulatory Commission Page 2 January 23, 2024 |
| | |
| | cc (w/ Enclosures): |
| | |
| | NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant}} |
Revision as of 19:44, 5 October 2024
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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump ML22075A2192021-11-29029 November 2021 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0133, Rev. 0 - Swing Check Valve, P/N ESl50359 ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19029A1552018-12-27027 December 2018 10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1 ML18075A3552018-03-0606 March 2018 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML17114A0692017-04-19019 April 2017 Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML15223B2662015-08-0707 August 2015 Part 21 Report - Crane Nuclear Pressure Seal Valve with Retaining Rings ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance ML15134A0162015-05-0101 May 2015 Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML14309A5292014-10-31031 October 2014 Closure of 10 CFR Part 21 Interim Report - Engine Systems, Inc., Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14318A1962014-09-0505 September 2014 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14216A3772014-07-30030 July 2014 Part 21 Report - Incorrect Industrial Irradiator Dose ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14189A4172014-07-0707 July 2014 Closure of 10 CFR Part 21 Interim Report - Limitorque Valve Motor - Motor Operator of SMB-0 Valve Actuator ML14192A0382014-07-0303 July 2014 Part 21 Report Incorrect Industrial Irradiator ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14069A4672014-02-26026 February 2014 Part 21 Report Involving a Potential Manufacturing Defect in Replacement Masterpact Cradles ML13260A0772013-09-12012 September 2013 10 CFR Part 21 Interim Report - General Electric (GE) Hitachi Nuclear Energy - Sbm Type Manual Switch ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13094A1772013-03-18018 March 2013 Notice to the U.S. Nuclear Regulatory Commission of a Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters Manufactured by Aaf ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML13008A3212013-01-0404 January 2013 Anti-Rotation Pin Failure in Anchor Darling (Flowserve) Double Disc Gate Valve ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML1127000672011-09-26026 September 2011 GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML11115A0392011-04-14014 April 2011 Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1025201572010-08-16016 August 2010 Initial Exam 2010-301 Final Administrative Documents ML1018907392010-07-0101 July 2010 Part 21 Report Concerning Failure of Turbine Overspeed Reset Control Valve Diaphragm ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0511602412005-04-14014 April 2005 Thermo Electron Svioc, SV18C and SV28C Series Recorders ML0506302442005-03-0202 March 2005 Part 21 Report Concerning MCPR Limits and MCPR Monitoring ML0501902562005-01-14014 January 2005 Non-Emergency Event Report from Framatome Anp, Inc ML0232901622002-11-18018 November 2002 Final Report, Stability Option III: Possible Successive Confirmation Count Resets - Not Reportable 2024-06-23
[Table view] Category:Letter
MONTHYEARIR 05000259/20240102024-11-12012 November 2024 Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010 IR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry 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 ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant 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 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 ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision 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 IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24151A6322024-05-30030 May 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-03
[Table view] |
Text
TENNESSEE VALLEY 1\\14 AUTHORITY
Post Office Box 2000, Decatur, Alabama 35609-2000
January 23, 2024
10 CFR 21.21
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Browns Ferry Nuclear Plant, Units 2 Renewed Facility Operating License No. DPR-52 NRC Docket No. 50-260
Subject:
Final Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump
References:
Letter from TVA to NRC, Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump, dated December 1, 2023 (ML23335A072)
On December 1, 2023, the Tennessee Valley Authority (TVA) submitted an interim Part 21 report regarding a defective overload relay at Browns Ferry Nuclear Plant (BFN). On October 2, 2023, a new overload relay was found to be defective during post-maintenance testing on a circuit breaker for the BFN, Unit 2, Reactor Core Isolation Cooling (RCIC) condensate pump. This QA1 part (DBC069X) had previously passed receipt inspection in April 2023 as part of a bulk order of 90 relays of this same type, of which, 82 remained in stock. This issue was promptly entered into the BFN Corrective Action Program (CAP) as Condition Report (CR) 1883872.
The manufacturer, GE-Hitachi (GEH), has inspected and tested the relay. Based upon TVAs evaluation of GEHs report, BFN Engineering had concluded that this is not a Part 21 reportable issue.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact David Renn, Site Licensing Manager, at (256) 729-2636.
Respectfully,
M.Sivaraman Site Vice President U.S. Nuclear Regulatory Commission Page 2 January 23, 2024
cc (w/ Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Project Manager - Browns Ferry Nuclear Plant