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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 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 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 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) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter 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 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-24-010, 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-24-024, 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-24-033, 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 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 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-24-025, 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
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 November 21, 2016 Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - FULL TRANSITION TO THE REACTOR OVERSIGHT PROCESS AND ASSESSMENT LETTER - DOCKET NO. 50-0391 On April 23, 2015, the U.S. Nuclear Regulatory Commission (NRC) issued the Watts Bar Nuclear Plant Unit 2 Reactor Oversight Process (ROP) Transition Plan (ADAMS Accession No. ML15096A204). This plan (enclosed) described the staffs plan for transition of the inspection and oversight programs from Inspection Manual Chapter (IMC) 2517, Watts Bar Unit 2 Construction Inspection Program, to the ROP. IMC 2517 established the staffs policy for the conduct of the Watts Bar Nuclear Plant Unit 2 construction and startup inspection program under IMC 2512 Construction Phase, IMC 2513 Preoperational Testing and Operational Preparedness Phase, and IMC 2514 Startup Testing Phase. The staff has completed the inspection activities required under each of these programs and determined that this completion provided reasonable assurance that each cornerstone of safety was ready to be monitored using the ROP. The closeout of the IMC 2517 Inspection Program is documented in NRC Inspection Report 05000391/2016609 (ADAMS Accession No. ML16326A199).
As of November 21, 2016, the NRC transitioned the remaining reactor safety cornerstones for the Watts Bar Nuclear Plant Unit 2 to the full oversight of the ROP as described in IMC 2515 and IMC 0305. This also represents the conclusion of the applicability of IMC 2517.
Accordingly, IMC 0609, Significance Determination Process (SDP), will be utilized to characterize the significance of inspection findings for all cornerstones. Likewise, IMC 0608, Performance Indicator (PI) Program, will be utilized to evaluate and process the PI data submitted by Watts Bar Nuclear Plant Unit 2. The Enclosure provides additional details on the transition of the PIs. Enforcement for any violations will be administered in accordance with the ROP, and the Commissions Enforcement Policy. Therefore, the NRC is fully implementing the ROP as described in IMC 2515 and IMC 0305 for Watts Bar Nuclear Plant Unit 2, effective as of November 21, 2016.
On November 2, 2016, the NRC completed a performance review of Watts Bar Nuclear Plant Unit 2. The NRC reviewed the most recent valid quarterly performance indicators and reviewed the most recent inspection results and enforcement actions from July 1, 2015 through October 31, 2016. This letter informs you of the NRCs assessment of your facility during this period and its plans for future inspections at your facility.
J. Shea 2 The NRC determined that overall, Watts Bar Nuclear Plant Unit 2 operated in a manner that preserved public health and safety and met all cornerstone objectives. Inspection findings and traditional enforcement violations issued across all cornerstones were determined to be of very low safety significance (i.e., Severity Level IV or Green). Additionally, PIs for previously transitioned cornerstones indicated that your performance was within the nominal, expected range (i.e., Green). Therefore, the NRC has determined that Watts Bar Nuclear Plant Unit 2 has entered the Licensee Response Column of the ROP Action Matrix, effective as of November 21, 2016. The NRC plans to conduct ROP baseline inspections at your facility.
However, in accordance with the Transition Plan, the PIs for Initiating Events indicators IE01 and IE03 and Mitigating Systems indicators MS06, MS07, MS08, MS09, and MS10 are not yet valid and will be subject to augmented inspections until declared fully valid.
On August 10, 2016, during the Mid-Cycle assessment of the Watts Bar Nuclear Plant, the NRC identified a Safety Conscious Work Environment (SCWE) cross-cutting theme due to the March 23, 2016, letter entitled, Chilled Work Environment for Raising and Addressing Safety Concerns at the Watts Bar Nuclear Plant (ML16083A479). However, inspectors have not identified any safety significant violations due to this SCWE theme. The NRC plans to maintain a focused oversight and inspection of this theme in accordance with the ROP inspection program. This may include focused problem identification and resolution samples to confirm your corrective actions have been effective through baseline inspection samples.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's "Agency Rules of Practice and Procedure," a copy of this letter, and its Enclosure, will be made available electronically for public inspection in the NRC Public Document Room, or from the NRC's Agencywide Documents Access and Management System (ADAMS); accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
Sincerely, Leonard D. Wert, Jr.
Deputy Regional Administrator for Operations Docket No. 50-0391 License No. NPF-96
Enclosure:
Reactor Oversight Process Transition Plan For Watts Bar Nuclear Plant, Unit 2
Letter to Joseph W. Shea from Leonard D. Wert, Jr. dated November 21, 2016
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 2 - FULL TRANSITION TO THE REACTOR OVERSIGHT PROCESS AND ASSESSMENT LETTER - DOCKET NO. 50-0391 DISTRIBUTION:
S. Price, RII S. Maxey, RII RIDSNRRDIRS PUBLIC
ML16326A210 SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP/BR6 RII:DRP/BR6 RII:DRP RII:DRS RII:DCO HQ:NRR/DIRS SIGNATURE * * * * * /RA via Email/
NAME A. Wilson A. Blamey J. Munday A. Gody W. Jones M. King DATE 11/9/2016 11/9/2016 11/10/2016 11/10/2016 11/10/2016 11/16/2016 E-MAIL COPY YES NO YES NO YES NO YES NO YES NO YES NO OFFICE RII:ORA RII:ORA SIGNATURE * /RA/
NAME L. Dudes L. Wert DATE 11/18/2016 11/21/2016 E-MAIL COPY YES NO YES NO YES NO YES NO YES NO