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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 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
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February 17, 2021 EA-16-061 Mr. Jim Barstow Vice President, Nuclear Regulatory Affairs & Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
CLOSURE OF CHILLING EFFECT LETTER - CHILLED WORK ENVIRONMENT FOR RAISING AND ADDRESSING SAFETY CONCERNS AT THE WATTS BAR NUCLEAR PLANT
Dear Mr. Barstow:
The purpose of this letter is to inform you of the Nuclear Regulatory Commissions (NRCs) decision to close the March 23, 2016, Chilling Effect Letter (CEL), which focused on the work environment at Tennessee Valley Authority's (TVAs) Watts Bar Nuclear Plant (WBN). This decision is based on the NRCs determination that TVA has satisfied the CEL closure criteria identified in the NRCs August 31, 2018, Assessment Follow-up Letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18242A458). The decision to close the subject CEL has no bearing on the Confirmatory Orders (COs) issued to TVA in 2009 (ADAMS Accession No. ML093510993) and 2017 (ADAMS Accession No. ML17208A647),
which resulted from violations of employee protection requirements. The NRC continues to evaluate the safety culture at all three TVA sites through the reactor oversight process.
The remainder of this letter provides additional details of the NRCs bases for closing the CEL.
Background
On March 23, 2016, the NRC issued a CEL (ADAMS Accession No. ML16083A479) regarding chilled work environment issues at WBN. This letter was issued after the NRC concluded that a chilled work environment existed in the operations department, as indicated by a perception among operators that they were not free to raise safety concerns without fear of retaliation.
On April 22, 2016, TVA provided a response to the CEL, which included a description of the immediate actions taken and the corrective actions planned to address the chilled work environment (ADAMS Accession No. ML16113A228). On April 12, 2017, TVA provided an update on the status of the corrective actions (ADAMS Accession No. ML17102B658).
In 2018, as a result of an increase in allegations received from Watts Bar personnel, the NRC performed a safety conscious work environment (SCWE) follow-up inspection at WBN and determined that a chilled work environment existed in the radiation protection (RP) department.
Due to the chilled work environment identified in the RP department and concerns related to the identification and evaluation of department-specific work environment trends, the NRC concluded that the 2016 CEL could not be closed. In an Assessment Follow-up Letter dated
J. Barstow 2 August 31, 2018, (ADAMS Accession No. ML18242A458), the NRC informed TVA that, due to the amount of time the CEL had remained open, the NRC opened a SCWE cross-cutting issue (CCI). That letter went on to define common criteria for closing both the CEL and the CCI.
Since the issuance of the CEL and CCI, TVA has made multiple organizational changes that have resulted in an improved safety culture.
NRC Activities Supporting CEL Closure During the period from 2016 to the present, the NRC staff reviewed TVAs corrective actions to address the work environment issues at WBN. These reviews took the form of inspections, interviews with plant staff, and assessments of allegations received from WBN personnel.
Beginning in late 2016, the NRC staff performed inspections at WBN to review TVAs root cause analyses, completed corrective actions, compliance with the 2009 and 2017 COs, metrics and measures TVA implemented to monitor progress, and the results of independent safety culture surveys and assessments performed in 2017 and 2019. These inspections included SCWE follow-up inspections in December 2016, February 2018, June 2018, January 2019, and October 2019. The NRC also performed additional safety culture inspections in June 2020 and October 2020.
The dedicated SCWE inspections that occurred from 2018 to 2020 involved interviews of over 290 employees and over 680 hours0.00787 days <br />0.189 hours <br />0.00112 weeks <br />2.5874e-4 months <br /> of direct inspection. This effort was supplemented by resident inspector presence which included daily monitoring and periodic validation of SCWE inspection results. During the inspections that occurred in 2018 to 2020, WBN employees interviewed indicated that they felt free to raise safety concerns through multiple avenues (e.g.,
discussions with management, corrective action program (CAP), Employee Concerns Program (ECP), or directly to NRC). In addition, the NRC has observed improvement in ECP investigations of concerns, pulsing survey results, safety culture assessments, nuclear safety culture monitoring panel processes, and other methods used to monitor safety culture and SCWE. The NRC has determined that TVAs corrective actions to address the identified safety culture issues were adequate, and the NRC has also noted a steady downward trend in allegations from WBN since the SCWE CCI was issued.
NRCs Decision to Close the CEL Based on the results of the inspections listed above, the NRC determined that the closure criteria established in the Watts Bar Annual Assessment Follow-Up Letter dated August 31, 2018, are met. Specifically, in evaluating the scope of efforts and progress in addressing these issues, the NRC determined that TVA recognized the issues and has effectively implemented a range of corrective actions. Further, the NRC concluded that TVAs actions, are adequate to address the underlying issues that led to the issuance of the CEL. These actions included implementation of new programs such as the nuclear safety culture monitoring panel, employee issue tracking matrix, and ECP pulsing surveys which improved the safety conscious work environment at WBN. Therefore, the NRC considers the CEL dated March 23, 2016, to be closed. In addition, the NRC will recommend closure of the CCI through the annual assessment process. Notwithstanding this conclusion, the NRC will continue to monitor TVAs activities to maintain a safety conscious work environment at WBN through the Reactor Oversight Process.
J. Barstow 3 This letter and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Laura A. Dudes Regional Administrator Docket Nos. 05000390 and 05000391 License Nos. NPF-90 and NPF-96 cc: Distribution via LISTSERV
ML21048A200 OFFICE RII: DRP RII:DRP RII: EICS RII:OGC RII:ORA/RC RII: ORA NAME T. Stephen M. Miller M. Kowal B. Clark S. Price L. Dudes DATE 02/11/2021 02/11/2021 02/10/2021 02/11/2021 02/11/2021 02/17/2021