|
---|
Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML22098A1172022-03-29029 March 2022 Engine Systems, Inc. Report No. 10CFR21-0134, Rev. 0 - 10CFR21 Reporting of Defects and Non-Compliance - (Emo Cylinder Head with Fireface Thickness Below Specification Cylinder Head P/N 40121485) ML21096A1142021-04-0606 April 2021 Ametek Solidstate Controls - Updated Interim Notifcation 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 ML19210D4342019-07-11011 July 2019 Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 ML19190A0432019-06-28028 June 2019 Discusses Proprietary Information for Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19029A1552018-12-27027 December 2018 10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1 ML18353A4282018-11-30030 November 2018 Engine Systems, Inc., 10CFR21-0123, Rev. 0, for a 10CFR21 Reportable Condition on Emd Fuel and Soakback Pumps ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML14042A2002014-01-21021 January 2014 Part 21 Report Regarding Non-Conformance of an Electrical Tubular Water Heater ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification IR 05000391/20130032013-08-21021 August 2013 Construction Deficiency Report 50-391/2013-03 - Failure to Implement Plant Changes - Final Report ML13240A0062013-08-21021 August 2013 Construction Deficiency Report 50-391/2013-03 - Failure to Implement Plant Changes - Final Report 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 ML12326A7142012-11-21021 November 2012 Fourth Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries Lll and Lv ML12206A0552012-07-24024 July 2012 Second Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries III and IV ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12097A3162012-03-0202 March 2012 Part 21 Report - Rosemont Pressure Tranmitters Out of Tolerance Condition ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12061A2682012-02-28028 February 2012 Part 21 Report - Potential Minimum Wall Violation on Seismic Plate Valve Bodies ML11220A3492011-08-0505 August 2011 Notification of Potential Part 21 Potential Defect in Qualtech Np Safety Related Motor Control Center Buckets ML11115A0392011-04-14014 April 2011 Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0520003332005-07-14014 July 2005 Part 21 Communication: Circuit Breaker Replacement Primary Bushings Not Tested to ANSI Standards ML0511602412005-04-14014 April 2005 Thermo Electron Svioc, SV18C and SV28C Series Recorders 2024-05-17
[Table view] Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) 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 IR 05000390/20243012024-10-17017 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 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 IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to 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-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to 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-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 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 ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, 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 Testing (WBN-TS2024-06-25025 June 2024 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 Testing (WBN-TS 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) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 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 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 IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements 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 CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
[Table view] Category:Part 21 Correspondence
MONTHYEARML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML15105A3462015-03-23023 March 2015 NSAL-15-2 - Impact of a Break in the Reactor Coolant Pump No. 1 Seal Leak-off Line Piping on Seal Leakage During a Loss of Seal Cooling Event ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification ML12326A7142012-11-21021 November 2012 Fourth Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries Lll and Lv ML12206A0552012-07-24024 July 2012 Second Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries III and IV ML0828003372008-10-0303 October 2008 Namco, Transmittal of 10CFR Part 21 Report - Thread Sealant Issue ML0714302622007-05-17017 May 2007 10 CFR Part 21 Report Concerning 3 and 4 Borg Warner Check Valves, Amendment of Information Previously Supplied ML0529103892005-10-13013 October 2005 Part 21 Communication: Testing to ANSI Standards Complete on Circuit Breaker Replacement Primary Bushings 2017-06-07
[Table view] |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 July 24,2012 10 cFR 21 .21(a)(2)
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Second lnterim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries lll and lV
References:
- 1. Letter from TVA to NRC, Licensee Event Report 39012012-001, "Failure to Meet Technical Specifications due to lssues Associated with Vital Battery Surveillance Program," dated March 16,2012 (ADAMS Accession No. ML12076A180)
- 2. Letter from TVA to NRC, "10 CFR 21 Interim Report - Unexpected Degradation of Vital Batteries lll and lV," dated May 25,2012 (M112145A670)
On March 16,2012, the Tennessee Valley Authority (TVA) submitted Licensee Event Report (LER) 39012012-001, "Failure to Meet Technical Specifications due to lssues Associated with Vital Battery Surveillance Program." The LER described an incident where the acceptance criterion of Technical Specification Surveillance Requirement 3.8.4.14 was not met due to unexpected degradation of Vital Batteries lll and lV.
Preliminarily, TVA determined that a manufacturing deficiency was the direct cause of the unexpected degradation, and on March 26,2012, it was determined that a possible reportable condition could exist pursuant to 10 CFR 21, "Reporting of Defects and Noncompliance."
On May 25,2012, TVA submitted an Interim Report pursuant to the reporting requirements of 10 CFR 21.21(aX2). TVA continues to investigate this matter; however, the investigation will not be completed within 60 days from the May 25,2O12 letter.
U.S. Nuclear Regulatory Commission Page 2 July 24,2012 Therefore, pursuant to the reporting requirements of 10 CFR 21.21(a)(2), this Interim Report is being submitted. The enclosure to this letter provides information required by 10 CFR 21.21(aX2) for the Interim Report of this condition.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact D. K. Guinn, WBN Site Licensing Manager, at (423) 365-1 589.
Respectfully, D. E. Grissette Site Vice President Watts Bar Nuclear Plant
Enclosure:
Second Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries lll and lV cc (Enclosure):
NRC Regional Administrator - Region ll NRC Senior Resident Inspector - Watts Bar Nuclear Plant
ENCLOSURE Second Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries lll and lV Name and Address of the Individual Makins the Interim Report Mr. D. E. Grissette Site Vice President Watts Bar Nuclear Plant Tennessee Valley Authority 1270 Highway 68 Spring City, TN 37381 Description of the Deviation or Failure to Complv that is beinq Evaluated On March 16,2012, the Tennessee Valley Authority (TVA) submitted Licensee Event Report (LER) 39012012-001, "Failure to Meet Technical Specifications due to lssues Associated with Vital Battery Surveillance Program." The LER described an incident where the acceptance criterion of Technical Specification Surveillance Requirement (SR) 3.8.4.14 was not met due to unexpected degradation of Vital Batteries lll and lV.
Vital Battery lll failed to meet the acceptance criterion of the battery capacity test in accordance with Technical Specification SR 3.8.4.14 on November 21, 2011. During the performance of the root cause analysis for the unexpected degradation of Vital Battery lll, an independent engineering analysis of the completed capacity test surveillance package for Vital Battery lV determined that the recorded results of the Vital Battery lV battery capacity test performed on February 10,2011 were incorrect, and that the battery capacity test for Vital Battery lV did not meet the acceptance criterion of Technical Specification SR 3.8.4.14. Therefore, both Vital Batteries lll and lV failed to meet the Technical Specification SR 3.8.4.14 acceptance criterion for the referenced capacity tests. Vital Batteries lll and lV have been replaced and returned to service. .
Vital Batteries lll and lV were approximately 16 years old when they failed their capacity tests, and had a vendor qualified service life of 20 years. Both batteries were maintained and operated in a manner that is consistent with vendor requirements and the recommendations of the Institute of Electrical and Electronics Engineers (IEEE) standards IEEE 450-1980 and IEEE 450-1995. Therefore, there were no known conditions to promote premature aging or damage of Vital Batteries lll and lV. The Tennessee Valley Authority (TVA) preliminarily determined that a manufacturing deficiency associated with the forming of the Vital Batteries lll and lV cells' positive plates was the direct cause of the unexpected degradation of Vital Batteries lll and lV.
This determination was based on the initial results of the vendor's destructive failure analysis. The final results of the vendor's analysis have not yet been provided to TVA.
ENCLOSURE Second Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries llland lV Evaluation Status The vendor is analyzing cells from Vital Batteries lll and lV to determine the cause of the unexpected degradation. Upon receipt of the vendor's final report, TVA will evaluate the vendor's results and determine if this condition is reportable pursuant to 10 cFR 21.
Date on which Evaluation will be Completed The evaluation will be completed by September 22,2012 or a follow-up Interim Report will be submitted pursuant to 10 CFR 21.21(a)(2).