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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 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 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 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 ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers 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) ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-068, 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 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 ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve 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) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 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 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision 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-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 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 ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation 2024-02-01
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 July 31, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
The Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project Plan - July 2013 Status Report
Reference:
TVA letter to NRC, "Additional Information Regarding March 28, 2013, Public Meeting with NRC Regarding the Tennessee Valley Authority's (TVA)
Commercial Grade Dedication Recovery Project," dated April 30, 2013 (ML13123A163)
The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) staff with the initial Commercial Grade Dedication Recovery Project Quarterly Update.
In Enclosure 2 of the referenced letter, Tennessee Valley Authority (TVA) provided the Nuclear Regulatory Commission (NRC) with a TVA Nuclear Power Group Commercial Grade Dedication Recovery Project Action Plan Summary that included Commercial Grade Dedication Recovery Project Milestones. In Milestone 4, TVA stated that quarterly updates would be provided to the NRC starting in July 2013 and that the updates would include any failures found in either the installed equipment review or warehouse inventory review along with an evaluation of safety significance of such failures for the installed items.
Printed on recycled paper
Nuclear Regulatory Commission Page 2 July 31, 2013 From April 2013 to present, the Commercial Grade Dedication (CGD) Recovery Project Team has identified 22,324 unique Catalog Identifiers (CATIDs) that have been generated for CGD items across the TVA Nuclear Power Group Fleet since September 1995, when significant changes were made to 10 CFR Part 21. Of this population, there are 13,175 unique CATIDs that were either not purchased or not installed. These CATIDs will require additional verification and documented disposition, as appropriate. The CGD Recovery Project Team has determined that the remaining 9,149 unique CATIDs have been either purchased or installed in a TVA nuclear plant and will require evaluation and disposition.
The CGD Recovery Project is evaluating the unique CATIDs in groups where possible. In many cases, several CGD packages have been generated for the same unique CATID due to the number of years of plant operations under evaluation.
The status provided below documents the progress to date based on accounting for the applicable number of unique CATIDs. CGD packages reviewed prior to April 2013, including those reported during the March 2013 NRC meeting, are captured in the number of unique CATIDs accounted for in this letter.
As of July 26, 2013, the TVA CGD Recovery Project Weekly Report indicated that from the population of 13,175 CATIDs that were either not purchased or not installed, 3,591 CATIDs have been verified via an additional data search to not exist in inventory or in the operating units.
As of July 26, 2013, the TVA CGD Recovery Project Weekly Report indicated that from the population of 9,149 CATIDs that were purchased and are either in inventory or installed, 2,154 CATIDs have been evaluated and dispositioned.
Two issues were identified during warehouse inventory reviews and entered into the Corrective Action Program. Service Request 755044 was initiated to identify and address failed current carrying capacity of two Square D Overload Heaters (CATID CAE345C) that were in inventory.
Both overload heaters failed and were disposed of appropriately, due to the destructive nature of the test. In accordance with the CGD Recovery Project Plan, further evaluation is underway to determine the details of the testing performed and the impact to the item's ability to perform its intended safety function. No items associated with CATID CAE345C were issued for plant installation.
Service Request 755092 was initiated to identify and address failed dimensional tests for four of six couplings (CATID BKG441 M) tested. The four failed couplings were disposed of appropriately. The two couplings that passed the dimensional test were issued for installation.
There are no additional CATID BKG441M couplings in inventory and there were no previous issues or returns. In accordance with the CGD Recovery Project Plan, further evaluation is underway to determine the details of the dimensional criteria and the impact to the item's ability to perform its intended safety function.
In addition to the above, a Quality Assurance (QA) Finding regarding the Conditional CGD process was recently entered into the TVA Corrective Action Program. Problem Evaluation
Nuclear Regulatory Commission Page 3 July 31, 2013 Report (PER) 579298 states that the failure to follow established procedures has resulted in an adverse trend to adequately document or perform Critical Characteristics for Acceptance Testing associated with conditional CGD items. TVA has put interim actions in place to arrest the adverse trend. The QA Finding will be evaluated and dispositioned in accordance with the Corrective Action Program.
Should the resolution of PER 579298 impact the scope or results of the CGD Recovery Project, details will be provided in the next quarterly report.
There are no new regulatory commitments contained in this letter. Should you have any questions, please contact John Laffrey at (423) 751-3262.
Respectfully, W. Shea ice Piresident, Nuclear Licensing cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Sequoyah Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant