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EPID:L-2019-LLA-0005, Package: Letter to P. Noss Authorization for Shipment of the Model No. Bea Research Reactor Package with Rhode Island Nuclear Science Center Fuel Elements (Approved, Closed) |
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MONTHYEARML19112A1782019-04-22022 April 2019 NRR E-mail Capture - Point Beach; Seabrook; Turkey Point - Acceptance of Requested Licensing Action Amendment Request to Revise Technical Specifications to Adopt TSTF-563 Project stage: Acceptance Review ML19129A2192019-05-0707 May 2019 Enclosusafety Evaluation Report (Letter to P. Noss Authorization for Shipment of the Model No. Bea Research Reactor Package with Rhode Island Nuclear Science Center Fuel Elements) Project stage: Approval ML19129A2162019-05-0707 May 2019 Package: Letter to P. Noss Authorization for Shipment of the Model No. Bea Research Reactor Package with Rhode Island Nuclear Science Center Fuel Elements Project stage: Request ML19129A2172019-05-0707 May 2019 Letter to P. Noss Authorization for Shipment of the Model No. Bea Research Reactor Package with Rhode Island Nuclear Science Center Fuel Elements Project stage: Other ML20322A0232020-12-0909 December 2020 Regulatory Audit Summary Related to Request to Implement Full Spectrum Tm LOCA Methodology for Loss-of-Coolant Accident Analysis and Tpbar Stress Analysis Project stage: Other 2019-05-07
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Category:Letter
MONTHYEARCNL-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 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 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 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) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 ML24009A1712024-02-16016 February 2024 Environmental Assessment and Finding of No Significant Impact Related to an Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods (EPID L-2023-LLA-0039) - Letter ML24019A0722024-02-14014 February 2024 Request for Withholding Information from Public Disclosure IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation 2024-09-05
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December 9, 2020 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 - REGULATORY AUDIT
SUMMARY
RELATED TO REQUEST TO IMPLEMENT FULL SPECTRUM' LOCA METHODOLOGY FOR LOSS-OF-COOLANT ANALYSIS TPBAR STRESS ANALYSIS (EPID L-2019-LLA-0005)
Dear Mr. Barstow:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated January 17, 2020, Tennessee Valley Authority (TVA) submitted a license amendment request that would replace the loss-of-coolant accident (LOCA) analysis evaluation model references with reference to the FULL SPECTRUM' Loss-of-Coolant Accident (FSLOCA') Evaluation Model analysis applicable to Watts Bar Nuclear Plant, Units 1 and 2, with replacement steam generators.
To enhance the review of TVAs request, the NRC staff conducted an audit of supporting documents from April 27, 2020, to June 26, 2020. The staff audited the requested documents to confirm certain information relied upon in the license amendment request. A summary of the regulatory audit is enclosed.
The NRC staff did not identify any significant issues during the audit. However, the staff did identify the need for additional information related to the topic of the audit. Separate correspondence containing a request for additional information was transmitted to Mr. Russ Wells on July 14, 2020.
Sincerely,
/RA/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-390 and 50-391
Enclosure:
Regulatory Audit Summary cc: Listserv
REGULATORY AUDIT
SUMMARY
RELATED TO LICENSE AMENDMENT REQUEST REGARDING IMPLEMENTATION OF FULL SPECTRUM' LOCA METHODOLOGY FOR LOSS-OF-COOLANT ANALYSIS TPBAR STRESS ANALYSIS TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-390 AND 50-391
1.0 BACKGROUND
A regulatory audit is a planned license or regulation-related activity that includes the examination and evaluation of docketed and non-docketed information. The audit was conducted with the intent to gain understanding, to verify information, and to identify information that will require docketing to support the basis of a licensing or regulatory decision.
By letter dated January 17, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20017A338), the Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) to the U.S. Nuclear Regulatory Commission (NRC) for Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2, Application to Implement the FULL SPECTRUM'1 LOCA (FSLOCA'1) Methodology for Loss-of-Coolant Accident (LOCA)
Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04). The proposed changes would revise Watts Bar, Units 1 and 2, Technical Specification 5.9.5, Core Operating Limits Report, to replace the LOCA analysis evaluation model references with reference to the FULL SPECTRUM' Loss-of-Coolant Accident (FSLOCA') Evaluation Model analysis applicable to Watts Bar, Units 1 and 2, with replacement steam generators; revise the Watts Bar, Unit 2, Operating License Condition 2.C(4),
to reflect the implementation of the FSLOCA Evaluation Model methodology; and revise Watts Bar, Unit 1, Technical Specification 4.2.1, Fuel Assemblies, to delete discussion of Zircaloy fuel rods. TVA also requested approval of the new LOCA-specific Tritium Producing Burnable Absorber Rod (TPBAR) stress analysis methodology to evaluate the integrity of the TPBARs for conditions expected during a large-break LOCA.
The NRC staff performed a preliminary review of the LAR and determined that a regulatory audit would assist in the timely completion of the review. The regulatory audit was performed consistent with NRC Office of Nuclear Reactor Regulation Office Instruction LIC-111, Revision 1, Regulatory Audits, dated October 31, 2019 (ADAMS Accession No. ML19226A274).
2.0 AUDIT ACTIVITIES AND RESULTS The NRC staff conducted a regulatory audit that consisted of a remote audit from April 27, 2020, to June 26, 2020. The audit plan was provided to TVA on April 27, 2020, and was revised on Enclosure
June 2, 2020 (ADAMS Accession Nos. ML20120A021 and ML20155K766, respectively). The list of documents uploaded by the licensee in response to the NRC staffs request and examined by the audit team is provided in Section 4.0 below.
The remote audit was conducted using an online portal and teleconferencing capabilities. The purpose of the audit was to (1) examine several analyses or documents referenced in the LAR but not provided as part of the LAR, and (2) identify any information that would be required from the licensee to be provided on the docket for the NRC to render a staff finding to support the safety evaluation.
The NRC staff examined the documents identified in Section 4.0 below and held an audit entrance call with members of TVA on April 30, 2020, regarding the LAR under review. The collective results of the regulatory audit were used by the NRC staff to finalize requests for additional information (RAIs).
At the conclusion of the audit, the NRC staff determined that additional information would be needed in order for the staff to complete the review of the LAR. An RAI was issued on July 14, 2020 (ADAMS Accession No. ML20196L862), for the following issues:
Details of the TPBAR cladding stress analysis methodology using the WCOBRA/TRAC-TF2 code Details of the thermal creep rupture and cladding burst failure mode analyses Details of the statistical approach similar to that used in the FSLOCA evaluation model to demonstrate compliance with Title 10 of the Code of Federal Regulations Section 50.46 acceptance criteria is used for the LOCA-specific TPBAR stress analysis, including inputs and stress intensities Acceptance criteria that ensure TPBAR structural integrity as listed in Table 4.3.2-1 of the LAR Details of Monte Carlo style statistical analysis where tolerance limits are constructed for the figures of merit related to the TPBAR structural integrity A sixth request was issued; however, the nature of the request is proprietary.
TVA provided a response to the RAI by letter dated August 27, 2020 (ADAMS Accession No. ML20240A324), which addressed the NRC staffs request.
3.0 AUDIT PARTICIPANTS NRC M. Panicker D. Woodyatt K. Green TVA R. Wells C. Borelli M. Burzynski
Pacific Northwest National Laboratory R. Montgomery D. Paxton Westinghouse M. Shockling M. Rudakewiz J. Laird 4.0 DOCUMENTS PROVIDED IN ELECTRONIC READING ROOM WCAP-18429-P, Revision 0, Watts Bar Units 1 and 2 TPBAR [Tritium Producing Burnable Absorber Rod] Structural Integrity Analysis for the Large Break Loss-of-Coolant Accident (LBLOCA), Westinghouse, March 2019 TTP-1-31101, Revision 1, Development of a Metric for Evaluation of TPBAR Structural Integrity During LBLOCA Event, Westinghouse/TVA/PNNL [Pacific Northwest National Laboratory],
April 2018 PNNL-TTP-1-3123, Revision 1, Tritium Technology Program, Stainless Steel Burst Stress Curve Evaluation, PNNL/TVA, March 2020 PNNL TTP-3-721, Revision 1, High Temperature Fracture Models for Assessment of TPBAR Cladding Survivability During LOCA, PNNL/TVA, April 2020 PNNL TTP-3-714 Revision 0, Thermal Creep Rupture Model Development for Loc Behavior of TPBARs, PNNL/TVA, March 2020 Watts Bar, Units 1 and 2 (WAT/WBT), Input File Finalization for Phase 2 of the FULL SPECTRUM LOCA (FSLOCA) EM Analysis (CN-LIS-17-83)
Region I Final Break Spectrum and Uncertainty Analysis Input File Finalization for Watts Bar, Units 1 and 2 (WAT/WBT), with the FULL SPECTRUM LOCA (FSLOCA) Evaluation Model (CN-LIS-18-33)
Watts Bar, Units 1 and 2 (WAT/WBT), Input File Finalization for Phase 2 of the FULL SPECTRUM LOCA (FSLOCA) EM [Evaluation Model] Analysis (CN-LIS-17-83)
Region I Final Break Spectrum and Uncertainty Analysis Input File Finalization for Watts Bar, Units 1 and 2 (WAT/WBT), with the FULL SPECTRUM LOCA (FSLOCA) Evaluation Model (CN-LIS-18-33)
ML20322A023 *by e-mail OFFICE NRR/DORL/LPL2-2/PM* NRR/DORL/LPL2-2/LA* NRR/DSS/SFNB/BC*
BAbeywickrama NAME KGreen RLukes (LRonewicz for)
DATE 11/20/2020 11/20/2020 09/08/2020 OFFICE NRR/DORL/LPL2-2/BC* NRR/DORL/LPL2-2/PM*
NAME UShoop KGreen DATE 12/07/2020 12/09/2020