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MONTHYEARML19112A0522019-07-25025 July 2019 Federal Register Notice: Watts Bar Nuclear Plant, Units 1 and 2 - Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 Project stage: Approval ML19112A0112019-07-25025 July 2019 Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 Project stage: Approval 2019-07-25
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Category:Federal Register Notice
MONTHYEARML23073A2762023-04-0303 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) ML23073A2992023-04-0303 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) (FRN) ML22129A0712022-05-0909 May 2022 Federal Register Notice (Correction) ML22117A1862022-04-29029 April 2022 Exemptions from the Requirements of 10 CFR Part 26, Section 26.205(d)(7) (EPID L-2022-LLE-0017) (Exemption) ML21063A1372021-03-18018 March 2021 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity to Request Hearing,Order Imposing Procedures for SUNSI Document Access(Frn) ML21063A1362021-03-18018 March 2021 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, Opportunity to Request Hearing,Order Imposing Procedures for SUNSI Document Access(Lette ML20358A2192021-01-0505 January 2021 Cover Letter with Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Sig. Hazards Consideration, and Opportunity for Hearing SUNSI ML20358A2202021-01-0505 January 2021 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Sig. Hazards Consideration, and Opportunity for Hearing SUNSI ML20034D6422020-02-12012 February 2020 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures: March ML19337A0312019-12-11011 December 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 12/17/2019 ML19298A4772019-10-31031 October 2019 Federal Register Notice: Watts Bar Nuclear Plant, Units 1 and 2 - License Amendment Application; Opportunity to Comment; Request a Hearing, and Petition for Leave to Intervene ML19298A6472019-10-31031 October 2019 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Opportunity for a Hearing ML19241A2962019-09-0606 September 2019 Transmittal of Individual Federal Register Renotice for License Amendment Request TSTF-50 ML19241A2952019-09-0606 September 2019 Individual Federal Register Renotice for License Amendment Request TSTF-500 ML19112A0522019-07-25025 July 2019 Federal Register Notice: Watts Bar Nuclear Plant, Units 1 and 2 - Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 ML19112A0112019-07-25025 July 2019 Exemption from the Requirements of 10 CFR Section 50.46 and Appendix K to 10 CFR Part 50 ML19168A0842019-06-26026 June 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 07/02/2019 ML19085A2172019-03-29029 March 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 04/09/2019 ML19042A3062019-02-15015 February 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 2/26/2019 ML18332A0132019-02-0606 February 2019 Federal Register Notice ML18332A0142019-02-0606 February 2019 Environmental Assessment and Finding of No Significant Impact Related to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, NRC-2019-0046, Federal Register Notice2019-02-0606 February 2019 Federal Register Notice ML18306A4682018-11-0808 November 2018 Individual Notice of Consideration of Issuance of Amendments to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML18306A4802018-11-0808 November 2018 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing ML18295A7442018-10-25025 October 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 11/06/18 NRC-2014-0045, FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 22018-08-21021 August 2018 FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 2 ML18200A1922018-08-21021 August 2018 Withdrawal of Amd Request to Change Implementation Date for Emergency Action Level Scheme ML18200A2142018-08-21021 August 2018 FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 2 ML18173A1792018-08-0707 August 2018 OEDO-17-00070 - Notice of Issuance of Director'S Decision, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Japan C ML18189A0032018-07-11011 July 2018 FRN: Watts Bar Nuclear Plant, Unit 1, Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing NRC-2018-0140, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/20182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 ML18180A2182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 ML18172A3042018-06-22022 June 2018 Tennessee Valley Authority - License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene ML18173A0532018-06-22022 June 2018 Ind. Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards ... ML18128A3062018-06-0404 June 2018 Federal Register Notice on Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Application; Opportunity to Request a Hearing and to Petition for Leave to Intervene; Order Imposing Procedures (Docket Nos. 50-390 and 50-391; NRC-2018-01 ML18128A2932018-05-30030 May 2018 Letter, Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing ML18039A8922018-02-14014 February 2018 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034) L-2016-003, Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034)2018-02-14014 February 2018 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034) ML17353A1922017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 NRC-2017-0238, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 20182017-12-21021 December 2017 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 2, 2018 ML17200A0652017-08-30030 August 2017 OEDO-17-00070 - Acknowledgement FRN, Paul Gunter, Beyond Nuclear, 2.206 Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and ML17198A3292017-08-30030 August 2017 OEDO-17-00070 - Acknowledgement Letter, Paul Gunter, Beyond Nuclear, Petition for Emergency Enforcement Action Per 10 CFR 2.206 at Listed U.S. Reactors with Forged Components and Parts Manufactured at France'S AREVA-Le Creusot Forge and Jap ML16336A2212016-12-29029 December 2016 FRN: Watts Bar Nuclear Plant Unit 2 - Notice of Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene; SUNSI Order ML16336A2152016-12-20020 December 2016 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing NRC-2016-0202, Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 20162016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 ML16257A5172016-09-19019 September 2016 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 27, 2016 NRC-2016-0161, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 20162016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 ML16215A2272016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 ML16214A1342016-07-29029 July 2016 Individual Notice of Issuance of Amendment to Facility Operating License ML16159A0712016-07-29029 July 2016 Cover Letter for Individual Notice 2023-04-03
[Table view] 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
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UNITED STATES WASHINGTON, D.C. 20555-0001 July 25, 2019 Mr. Joseph W. Shea Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A Chattanooga, TN 37 402-2801
SUBJECT:
WAITS BAR NUCLEAR PLANT, UNITS 1 AND 2 - EXEMPTION FROM THE REQUIREMENTS OF 10 CFR SECTION-50.46 AND APPENDIX K TO 10 CFR PART 50 TO ALLOW THE USE OF OPTIMIZED ZIRLO' FUEL ROD CLADDING (EPID L-2018-LLE-0012)
Dear Mr. Shea:
The U.S. Nuclear Regulatory Commission has approved the enclosed exemption from specific requirements of Title 10 of the Code of Federal Regulations (10 CFR) Section 50.46 and Appendix K, "ECCS Evaluation Models," to 10 CFR Part 50 for the Watts Bar Nuclear Plant, Units 1 and 2. This action is in response to your application dated July 23, 2018 (Agencywide Documents Access and Management System Accession No. ML18205A492), which requested exemption from the above regulations to use Optimized ZIRLO' as an approved fuel rod cladding material.
A copy of the exemption is enclosed. The exemption has been forwarded to the Office of the Federal Register for publication.
Sincerely, p=-9 Michael J. Wentzel, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-390 and 50-391
Enclosure:
Exemption cc: Listserv
ENCLOSURE EXEMPTION
[7590-01-P]
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-390 and 50-391; NRC-2019-0138)
Tennessee Valley Authority; Watts Bar Nuclear Plant, Units 1 and 2 AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption; issuance.
SUMMARY
- The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued an exemption in response to a July 23, 2018, request from Tennessee Valley Authority (TVA or the licensee) to implement Optimized ZIRLO' fuel rod cladding at the Watts Bar Nuclear Plant (Watts Bar), Units 1 and 2.
DATES: The exemption was issued on July 25, 2019.
ADDRESSES: Please refer to Docket ID NRC-2019-0138 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods:
- Federal Rulemaking Web Site: Go to and search for Docket ID NRC-2019-0138. Address questions about NRC docket IDs to Jennifer Borges; telephone: 301-287-9127; e-mail: For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document.
- NRC's Agencywide Documents Access and Management System (ADAMS): You may obtain publicly-available documents online in the ADAMS Public Documents collection at ~=c:..::..:.=-'-'-'.!.=~~=~:...,..:..,.=~=~* To begin the search, select :...:..=~.:.::::::_:...==-=:.::=~~ and then select ~9ill..YJL§.2::.Q§.~!.l:l!:la~
==:..:.*" For problems with ADAMS, please contact the NRC's Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to The ADAMS accession number for each document referenced (if it is available in ADAMS) is provided the first time that it is mentioned in this document. In addition, for the convenience of the reader, the ADAMS accession numbers are provided in a table in the "Availability of Documents" section of this document.
- NRC's PDR: You may examine and purchase copies of public documents at the NRC's PDR, Room 01-F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Robert Schaaf, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-6020, e-mail: :...======:.:..=~
SUPPLEMENTARY INFORMATION:
I. Background TVA is the holder of Facility Operating License Nos. NPF-90 and NPF-96, which authorize operation of Watts Bar, Units 1 and 2, respectively. The licenses provide, among other things, that the facilities are subject to all rules, regulations, and orders of the NRC now or hereafter in effect. The facilities consist of pressurized-water reactors located in Spring City, Tennessee.
II. Request/Action By application dated July 23, 2018 (ADAMS Accession No. ML18205A492), TVA, pursuant to section 50.12 of title 1O of the Code of Federal Regulations (10 CFR),
"Specific exemptions," requested an exemption from certain requirements of 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems [ECCS] for 2
light-water nuclear power reactors," and appendix K, "ECCS Evaluation Models," to 10 CFR part 50 to allow the use of fuel rod cladding with Optimized ZIRLO' alloy for future reload applications. The regulations in 10 CFR 50.46 contain acceptance criteria for the ECCS for reactors fueled with zircaloy or ZIRLO' fuel rod cladding material. In addition, 10 CFR part 50, appendix K, requires that the Baker-Just equation be used to predict the rates of energy release, hydrogen concentration, and cladding oxidation from the metal/water reaction. The Baker-Just equation assumes the use of a zirconium alloy, which is a material different from Optimized ZIRLO'. The licensee requested the exemption because these regulations do not have provisions for the use of fuel rod cladding material other than zircaloy or ZIRLO'. Because the material specifications of Optimized ZIRLO' differ from the specifications for zircaloy or ZIRLO', a plant-specific exemption is required to support the reload applications for Watts Bar, Units 1 and 2.
This exemption request relates solely to the s.pecific type of cladding material specified in these regulations for use in light-water reactors. As written, the regulations presume use of either Zircaloy or ZIRL0' 1 fuel rod cladding. The exemption is required because Optimized ZIRLO' has a slightly different composition than Zircaloy or ZIRLO'. Therefore, TVA has requested an exemption to consider Optimized ZIRLO' as an approved fuel rod cladding material. TVA is not seeking an exemption from the acceptance and analytical criteria of 10 CFR 50.46 and appendix K to 10 CFR part 50.
The requirements regarding the acceptance and analytical criteria will be maintained.
Along with the exemption request, the submittal from TVA described above also contains a license amendment request to modify Technical Specifications 4.2.1, "Fuel Assemblies," and 5.9.5, "Core Operating Limits Report (COLR)," to allow the use of 1 "Optimized ZIRLO" and "ZIRLO" are trademarks or registered trademarks of Westinghouse Electric Company, LLC.
3
Optimized ZIRLO' as an approved fuel rod cladding material. This exemption and the proposed Technical Specification changes are subject to a concurrent review that is being documented in the safety evaluation with the license amendments (ADAMS Acce~sion No. ML19112A004).
The NRC has previously approved exemption requests that were similar in nature to that requested by TVA. Precedent exemptions have been approved for other pressurized-water reactor plants, including Beaver Valley Power Station, Units 1 and 2 (ADAMS Accession Nos. ML180228116 and ML17313A550); Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (ADAMS Accession Nos. ML17319A107 and ML17319A214); and Wolf Creek Generating Station, Unit 1 (ADAMS Accession Nos. ML16179A293 and ML16179A440).
Ill. Discussion Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 50 when: ( 1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. Under 10 CFR 50.12(a)(2),
special circumstances include, among other things, when application of the specific regulation in the particular circumstance would not serve, or is not necessary to achieve, the underlying purpose of the rule. The requested exemption to apply the acceptance criteria to Optimized ZIRLO' fuel rod cladding rather than Zircaloy or ZIRLO' at Watts Bar, Units 1 and 2, satisfies the criteria as described below.
A. Special Circumstances The special circumstance that necessitates the request for exemption to 10 CFR 50.46 and appendix K to 10 CFR part 50 is that neither of these regulations 4
explicitly allows the use of Optimized ZIRLO' fuel rod cladding material. The ultimate objective of 10 CFR 50.46 is to ensure that nuclear power reactors fueled with uranium oxide pellets within Zircaloy or ZIRLO' cladding must be provided with ECCS that must be designed to provide core cooling following postulated loss-of-coolant accidents. It has been demonstrated in the NRG-approved Westinghouse Topical Report WCAP-14342-A & CENPD-404-NP-A, Addendum 1-A (ADAMS Accession No. ML062080569) that the effectiveness of the ECCS will not be affected by a change from Zircaloy or ZIRLO' clad fuel to Optimized ZIRLO' clad fuel. Normal reload safety analyses will confirm that there is no adverse impact on ECCS performance.
The objective of 10 CFR 50.46(b)(2) and (b)(3) and paragraph I.A.5 of appendix K to 10 CFR part 50 is to ensure that cladding oxidation and hydrogen generation are appropriately limited during a loss-of-coolant accident and conservatively accounted for in the ECCS evaluation model. Appendix K of 10 CFR 50 requires that the Baker-Just equation be used in the ECCS evaluation model to determine the rate of energy release, cladding oxidation, and hydrogen generation. Westinghouse has shown in Addendum 1-A to WCAP-12610-P-A that the Baker-Just model is conservative in all post-loss-of-coolant accident scenarios with respect to the use of the Optimized ZIRLO' advanced alloy as a fuel cladding material.
B. The Exemption is Authorized by Law The NRC has the authority under 10 CFR 50.12 to grant exemptions from the requirements of 10 CFR part 50 upon showing proper justification. The fuel that will be irradiated at Watts Bar, Units 1 and 2, contains cladding material that does not conform to the cladding material that is explicitly defined in 10 CFR 50.46 and implicitly defined in appendix K to 10 CFR part 50. However, the criteria of these sections will continue to be 5
satisfied for the operation of the Watts Bar, Units 1 and 2, core containing Optimized ZIRLO' fuel cladding.
C. The Exemption Presents No Undue Risk to Public Health and Safety The standards for exemption are also satisfied since the exemption will not present an undue risk to public health and safety. The NRC-approved Westinghouse topical report discussed above has demonstrated that predicted chemical, thermal, and mechanical characteristics of the Optimized ZIRLO' alloy cladding are bounded by those approved for ZIRLO' under anticipated operational occurrences and postulated accidents. Reload cores are required to be operated in accordance with the operating limits specified in the Technical Specifications and COLR. Thus, the granting of this exemption request will not pose an undue risk to public health and safety.
D. The Exemption is Consistent with the Common Defense and Security The exemption request is to allow the licensee to use an improved fuel rod cladding material. The licensee has documented compliance with the conditions and limitations of the NRC safety evaluation regarding the use of Optimized ZIRLO' fuel rod cladding at Beaver Valley Power Station, Units 1 and 2, and has committed to ensuring compliance for future reloads in the current application for Watts Bar, Units 1 and 2. Use of Optimized ZIRLO' fuel rod cladding in the Watts Bar, Units 1 and 2, cores will not affect plant operations and is consistent with common defense and security.
E. Environmental Considerations A review has determined that the proposed amendments would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR part 20, or would change an inspection or surveillance requirement. However, the proposed amendments do not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant 6
increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendments meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendments.
IV. Conclusion Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12, the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Therefore, the Commission hereby grants TVA an exemption from the requirements of 10 CFR 50.46 and appendix K to 10 CFR part 50 to allow the use of Optimized ZIRLO' fuel rod cladding material at Watts Bar, Units 1 and 2. As stated in this notice, this exemption relates solely to the cladding material specified in these regulations.
Dated at Rockville, Maryland, this 25th day of July, 2019.
For the Nuclear Regulatory Commission.
Blake D. Welling, Deputy Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
7
LTR ML19112A011 FRN ML19112A052 *by memo **by e-mail OFFICE DORL/LPL2-2/PM DORL/LPL2-2/LA DSS/SRXB/BC* DSS/STSB/(A)BC** DMLR/MVIB/BC**
NAME NJordan BClayton JWhitman PSnyder DAlley (LRonewicz for)
DATE 4/26/2019 4/26/2019 10/5/2018 5/23/2019 5/22/2019 OFFICE DSS/SNPB/BC* OGC - NLO** DORL/LPL2-2/BC DORL/LPL2-2/PM MWentzel NAME RLukes KGamin UShoop (NJordan for)
DATE 10/5/2018 06/20/2019 7/23/2019 7/25/2019