Letter Sequence Other |
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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
[Table View] |
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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] |
Text
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
