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Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML22098A1172022-03-29029 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 ML12066A1182012-03-0202 March 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 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 2022-03-29
[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
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Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 November 21 , 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:
Fourth Interim 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)
- 3. Letter from TVA to NRC, "Second Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries lll and lV,"
dated July 24,2012 (ML12206A055)
- 4. Letter from TVA to NRC, "Third Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries lll and lV,"
dated Septem ber 17, 2012 (ML12261A473)
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.
U.S. Nuclear Regulatory Commission Page 2 November 21 ,2012 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 July 24,2012, TVA submitted a Second lnterim Report pursuant to the reporting requirements of 10 CFR 21 .21(a)(2). On September 17,2012, TVA submitted a Third lnterim Report pursuant to the reporting requirements of 10 CFR 21.21(a)(2). TVA continues to investigate this matter; however, the investigation will not be completed within 60 days from the September 17,2012letter.
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(a)(2) forthe Interim Report of this condition.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submiftal, 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:
Fourth 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 Fourth Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries lll and lV Name and Address of the Individual Makino 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 (T\/A) 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 fV 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.
ENCLOSURE Fourth Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries lll and lV Evaluation Status TVA has received the vendor's final report and is evaluating the results to determine if this condition is reportable pursuant to 10 CFR 21.
Date on which Evaluation will be Completed The evaluation will be completed by January 20,2013 or a follow-up lnterim Report will be submitted pursuant to 10 CFR 21.21(aX2).