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MONTHYEARML0204507012002-02-11011 February 2002 Unit - Request for Additional Information Re Tritium Production Program Interface Issue 7 Project stage: RAI ML0205800822002-02-19019 February 2002 Response to Request for Additional Information Re Tritium Production - Holtec Analysis. Submits New non-proprietary Version (Revision 3) of Holtec International Report HI-2012620 Project stage: Response to RAI ML0205806122002-02-21021 February 2002 License Amendment, FSAR Change for Revised Spent Fuel Cooling Analysis Methodology - TAC Nos. MB1807 and MB1884 Project stage: Other ML0205800052002-02-21021 February 2002 Responses to RAI Regarding Tritium Producing Burnable Absorber Rods (TPBARS) Project stage: Response to RAI ML0205804302002-02-21021 February 2002 Tennessee Valley Authority Response to NRC Request for Additional Information Re Tritium Producing Burnable Absorber Rods (TPBARS) at Watts Bar Nuclear Plant Project stage: Response to RAI ML0210003612002-04-0505 April 2002 Response to Request for Additional Information Re Tritium Production - Interface Issue Number 2 - Procurement and Fabrication Issues Project stage: Response to RAI ML0211905572002-04-25025 April 2002 Second Request for Additional Information Tritium Production Program Interface Issue 7 Project stage: RAI ML0212806302002-05-0808 May 2002 Request for Additional Information Re Tritium Production Program Interface Issue 5 Project stage: RAI ML0214401522002-05-21021 May 2002 Request for Additional Information Regarding Tritium Production - Interface Issue Number 7 Light Load Handling Systems Project stage: Request ML0214401422002-05-21021 May 2002 Request for Additional Information Re Tritium Production - Interface Issue Number 7 - Light Load Handling Systems Project stage: Request ML0214401352002-05-21021 May 2002 Request for Additional Information Re Tritium Production - Interface Issue Number 5 - Control Room Habitability Systems Project stage: Request ML0214901392002-05-23023 May 2002 Response to Request for Additional Information Re Radiological Impact Project stage: Response to RAI ML0221004492002-07-29029 July 2002 Request for Additional Information Tritium Production Program Project stage: RAI ML0221401972002-07-30030 July 2002 Tritium Production -- Post-LOCA Hot Leg Emergency Core Cooling System (ECCS) Recirculation Time -- Supplemental Information Project stage: Supplement ML0222601522002-08-0909 August 2002 Request for Risk-Informed Information Tritium Production Program Project stage: Request ML0831800942002-08-0909 August 2002 Plants - Request for Risk-Informed Information Tritium Production Program Project stage: Request ML0223209052002-08-20020 August 2002 Environmental Assessment and Finding of No Significant Impact for Incore Irradiation Services for the U. S. Department of Energy'S Tritium Production Program Project stage: Other ML0225409252002-09-23023 September 2002 Amendment No. 40, Irridiate Up to 2304 Tritium-Producing Burnable Absorber Rods in the Reactor Core Project stage: Acceptance Review ML0227502952002-09-23023 September 2002 Technical Specification Pages for Amendment No. 40, Irradiated Up to 2304 Tritium Producing Burnable Absborber Rods in the Reactor Core Project stage: Other ML0735205462008-01-18018 January 2008 Issuance of License Amendment 67 Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Approval ML0802203782008-01-18018 January 2008 Tech Spec Pages for Amendment 67 Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Other ML0821800942008-07-31031 July 2008 WCAP-16932-NP, Rev. 1, Control Rod Insertion Following a Cold Leg LOCA for Watts Bar Unit 1. Project stage: Request ML0821800932008-08-0101 August 2008 Watt'S Bar, Unit 1, Technical Specifications Change - Revision of Boron Requirements for Cold Leg Accumulators and Refueling Water Storage Tank. Project stage: Request ML0827502132008-10-0606 October 2008 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 (Tac No. MD9396) Project stage: Withholding Request Acceptance ML0828314472008-10-14014 October 2008 Request for Additional Information Regarding Analysis in Support of Control Rod Insertion Following a Cold Leg Loss-of -Coolant Accident (Tac MD9396) Project stage: RAI ML0829401702008-10-28028 October 2008 Request for Additional Information - Watts Bar Emergency Core Cooling System Boron Requirements Project stage: RAI ML0830401042008-11-0707 November 2008 Request for Additional Information - Watts Bar Emergency Core Cooling System Boron Requirements Project stage: RAI ML0833601912008-11-25025 November 2008 Response to Request for Additional Information Analysis in Support of Control Rod Insertion Following a Cold Leg Loss-of-Coolant Accident Project stage: Response to RAI ML0834303042008-12-0909 December 2008 Potential Schedule Impact Regarding Revision of Technical Specifications, Revision of Boron Requirements for Cold Leg Accumulators and Refueling Water Storage Tank. Project stage: Other ML0835101022008-12-19019 December 2008 Withdrawal of Questions Number 6 from Letter Dated October 28, 2008, Regarding Proposed Amendment to Revise Technical Specifications for Boron Requirements for the Cold Leg Accumulations and Refueling Water Storage Tank Project stage: Withdrawal ML0902202552008-12-31031 December 2008 Response to Request for Additional Information Emergency Core Cooling System Boron Requirements Project stage: Response to RAI ML0900900442008-12-31031 December 2008 Revised Technical Specifications Change WBN-TS-08-04 - Revision to the Maximum Number of TPBARS That Can Be Irradiated in the Reactor Core Per Cycle Project stage: Other ML0933507402009-01-0505 January 2009 Request for Information Regarding the Tritium Producing Burnable Absorber Rods (Tac No. ME2775) Project stage: RAI ML0900600402009-01-26026 January 2009 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 Project stage: Withholding Request Acceptance ML0909205062009-05-0404 May 2009 Issuance of Amendment Regarding the Maximum Number of Tritium Producing Burnable Assembly Rods in the Reactor Core Project stage: Approval ML1004703202010-02-0909 February 2010 Clarification Regarding the Number of Tritium Producing Burnable Absorber Rods in Operating Cycle 10 and Program Update Project stage: Other CNL-14-053, Notification of the Number of Tritium Producing Burnable Absorber Rods for the Operating Cycle 13 Reactor Core2014-04-0808 April 2014 Notification of the Number of Tritium Producing Burnable Absorber Rods for the Operating Cycle 13 Reactor Core Project stage: Other ML15030A5082015-01-30030 January 2015 Tritium Production Program, Updated Plans for Cycle 13 Operation and Updated Evaluation of the Radiological Impacts of Tritium Permeation Into the Reactor Coolant System Project stage: Other 2008-10-14
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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] Category:License-Operating (New/Renewal/Amendments) DKT 50
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 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 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) ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 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) 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 ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22257A0512022-11-0404 November 2022 Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A ML22276A1612022-10-24024 October 2022 Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22187A0192022-09-20020 September 2022 Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps ML22187A1812022-09-20020 September 2022 Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML22014A2062022-05-0404 May 2022 Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors ML21347A9672022-02-0101 February 2022 Correction of Errors Incurred During Issuance of the Initial Facility Operating License, and Issuance of License Amendment Nos. 6, 21, and 39 ML21306A2872022-01-25025 January 2022 Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement ML21334A2952022-01-18018 January 2022 Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement ML21334A3892022-01-12012 January 2022 Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis ML21271A1372021-12-16016 December 2021 Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level ML21189A3072021-11-0303 November 2021 Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21158A2842021-09-17017 September 2021 Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation ML21153A0492021-07-26026 July 2021 Issuance of Amendment No. 147 Regarding Change to Steam Generator Tube Inspection Frequency and Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-510 ML21161A2392021-06-24024 June 2021 Issuance of Amendment No. 54 Regarding Use of Temperature Adjustment to Voltage Growth Rate for the Generic Letter 95-05 Steam Generator Tube Repair Criteria ML21148A1002021-06-17017 June 2021 Issuance of Amendment No. 53 Regarding Neutron Fluence Calculation Methodology ML21099A2462021-05-14014 May 2021 Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21078A4842021-05-0505 May 2021 Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications ML21015A0342021-03-0909 March 2021 Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation ML21034A1692021-02-26026 February 2021 Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology ML20232C6222021-02-11011 February 2021 Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037 ML21027A1672021-02-0909 February 2021 Issuance of Amendment No. 48 Regarding Use of Alternate Probability of Detection Values for Beginning of Cycle in Support of Operational Assessment ML20350B4932021-01-25025 January 2021 Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21005A1252021-01-12012 January 2021 Correction of Errors Incurred During Issuance of License Amendment Nos. 43 and 45 ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20245E4132020-12-0808 December 2020 Issuance of Amendment Nos. 139 and 45 Regarding Revisions to Technical Specification 3.6.15, Shield Building ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20239A7912020-10-28028 October 2020 Issuance of Amendment Nos. 137 and 43 Regarding Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 541, Revision 2 ML20226A4442020-10-21021 October 2020 Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate ML20238C0612020-09-21021 September 2020 Correction of Typographical Error Incurred During Issuance of License Amendment No. 104 ML20167A1482020-08-19019 August 2020 Issuance of Amendment Nos. 136 and 41 Regarding the Automatic Transfer from a Unit Service Station Transformer to a Common Station Service Transformer ML20156A0182020-08-10010 August 2020 Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve ML20076A1942020-04-30030 April 2020 Issuance of Amendment Nos. 134 and 38 Regarding Adopting the Title 10 CFR Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants ML20057E2422020-03-30030 March 2020 Issuance of Amendment Nos. 133 and 37 Regarding Changes to Technical Specifications Pertaining to Diesel Generator Start Instrumentation (EPID-L-2020-LLA-0003) ML20028F7332020-02-28028 February 2020 Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 ML20024F8352020-02-24024 February 2020 Issuance of Amendment No. 35 Regarding One-Time Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML20015A4792020-01-30030 January 2020 Correction to Amendment No. 30 to Facility Operating License Npf-96 Regarding Use of Optimized Zirlo Fuel Rod Cladding ML19336C5192019-12-10010 December 2019 Issuance of Amendment Nos. 131 and 34 Regarding Correction to Unbalanced Voltage Relay Instrumentation Values ML19276E5572019-12-0909 December 2019 Issuance of Amendment Nos. 130 and 33 Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML19238A0052019-11-26026 November 2019 Issuance of Amendment Nos. 129 and 32 Regarding Changes to Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9 ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection 2024-01-29
[Table view] Category:Safety Evaluation
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 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 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 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) 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 ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22293A4082022-11-14014 November 2022 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML22257A0512022-11-0404 November 2022 Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A ML22276A1612022-10-24024 October 2022 Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22272A5682022-10-12012 October 2022 Authorization of Alternatives to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Operating and Maintenance Code ML22187A0192022-09-20020 September 2022 Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps ML22187A1812022-09-20020 September 2022 Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML22014A2062022-05-0404 May 2022 Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors ML22084A0012022-04-0505 April 2022 Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes ML22070A0022022-03-28028 March 2022 Review of the Fall 2021 Mid Cycle Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Report ML21306A2872022-01-25025 January 2022 Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement ML21334A2952022-01-18018 January 2022 Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement ML21334A3892022-01-12012 January 2022 Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis ML21271A1372021-12-16016 December 2021 Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level ML21189A3072021-11-0303 November 2021 Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21158A2842021-09-17017 September 2021 Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation ML21153A0492021-07-26026 July 2021 Issuance of Amendment No. 147 Regarding Change to Steam Generator Tube Inspection Frequency and Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-510 ML21161A2392021-06-24024 June 2021 Issuance of Amendment No. 54 Regarding Use of Temperature Adjustment to Voltage Growth Rate for the Generic Letter 95-05 Steam Generator Tube Repair Criteria ML21148A1002021-06-17017 June 2021 Issuance of Amendment No. 53 Regarding Neutron Fluence Calculation Methodology ML21099A2462021-05-14014 May 2021 Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21130A6012021-05-13013 May 2021 Correction of Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B ML21078A4842021-05-0505 May 2021 Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications ML21110A0372021-04-29029 April 2021 Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B ML21064A4082021-03-10010 March 2021 Correction of Safety Evaluation for License Amendment Nos. 143 and 50 (EPID L-2020-LLA-0005) (Non-Proprietary) ML21015A0342021-03-0909 March 2021 Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation ML21034A1692021-02-26026 February 2021 Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology ML20232C6222021-02-11011 February 2021 Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037 ML21027A1672021-02-0909 February 2021 Issuance of Amendment No. 48 Regarding Use of Alternate Probability of Detection Values for Beginning of Cycle in Support of Operational Assessment ML20350B4932021-01-25025 January 2021 Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20245E4132020-12-0808 December 2020 Issuance of Amendment Nos. 139 and 45 Regarding Revisions to Technical Specification 3.6.15, Shield Building ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20239A7912020-10-28028 October 2020 Issuance of Amendment Nos. 137 and 43 Regarding Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 541, Revision 2 ML20226A4442020-10-21021 October 2020 Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate ML20167A1482020-08-19019 August 2020 Issuance of Amendment Nos. 136 and 41 Regarding the Automatic Transfer from a Unit Service Station Transformer to a Common Station Service Transformer ML20156A0182020-08-10010 August 2020 Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve ML20076A1942020-04-30030 April 2020 Issuance of Amendment Nos. 134 and 38 Regarding Adopting the Title 10 CFR Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants ML20057E2422020-03-30030 March 2020 Issuance of Amendment Nos. 133 and 37 Regarding Changes to Technical Specifications Pertaining to Diesel Generator Start Instrumentation (EPID-L-2020-LLA-0003) ML20028F7332020-02-28028 February 2020 Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 ML20024F8352020-02-24024 February 2020 Issuance of Amendment No. 35 Regarding One-Time Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML19336C5192019-12-10010 December 2019 Issuance of Amendment Nos. 131 and 34 Regarding Correction to Unbalanced Voltage Relay Instrumentation Values 2024-01-29
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Text
January 18, 2008 Mr. William R. Campbell, Jr.
Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT REGARDING THE MAXIMUM NUMBER OF TRITIUM PRODUCING BURNABLE ASSEMBLY RODS IN THE REACTOR CORE (TAC NO. MD5430)
Dear Mr. Campbell:
The Commission has issued the enclosed Amendment No. 67 to Facility Operating License No. NPF-90 for Watts Bar Nuclear Plant, Unit 1 (WBN-1). This amendment is in response to your application dated April 25, 2007, as supplemented by letter dated August 22, 2007.
The amendment revises Technical Specification Surveillance Requirement 3.5.1.4, AAccumulators,@ and 3.5.4.3, ARefueling Water Storage Tanks,@ to remove the note limiting the number of tritium producing burnable absorber rods (TPBARs) to no more than 240. This change will also revise TS 4.2.1, AFuel Assemblies,@ to revise the maximum number of TPBARs that can be irradiated in the WBN-1 reactor core to 400.
A copy of the safety evaluation is also enclosed. Notice of issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/
Brendan T. Moroney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosures:
- 1. Amendment No. 67 to NPF-90
- 2. Safety Evaluation cc w/enclosures: See next page
ML073520546 Package No.: ML073530482 TS No.:ML080220378 NRR-058 OFFICE LPL2-2/PM LPL2-2/LA CVIB/BC SNPB/BC ITSB/BC OGC LPL2-2/BC NAME BMoroney RSola MMitchell AMendiola TKobetz NLO TBoyce By memo dtd By memo dtd EWilliams DATE 12/20/07 12/19/07 10/29/07 12/04/07 01/03/08 01/09/08 01/18//08 William R. Campbell, Jr.
Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:
Mr. Gordon P. Arent Ms. Beth A. Wetzel, Manager New Generation Licensing Manager Corporate Nuclear Licensing and Tennessee Valley Authority Industry Affairs 5A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Ashok S. Bhatnagar Senior Vice President Mr. Masoud Bajestani, Vice President Nuclear Generation Development Watts Bar Unit 2 and Construction Watts Bar Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P.O. Box 2000, EQB 1B 1101 Market Street Spring City, TN 37381 Chattanooga, TN 37402-2801 Mr. Michael K. Brandon, Manager Mr. James R. Douet Licensing and Industry Affairs Vice President Watts Bar Nuclear Plant Nuclear Support Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 3R Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael J. Lorek, Plant Manager Watts Bar Nuclear Plant Mr. H. Rick Rogers Tennessee Valley Authority Vice President P.O. Box 2000 Nuclear Engineering & Technical Services Spring City, TN 37381 Tennessee Valley Authority 3R Lookout Place Senior Resident Inspector 1101 Market Street Watts Bar Nuclear Plant Chattanooga, TN 37402-2801 U.S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Mr. Michael D. Skaggs, Site Vice President Spring City, TN 37381 Watts Bar Nuclear Plant Tennessee Valley Authority County Executive P.O. Box 2000 375 Church Street Spring City, TN 37381 Suite 215 Dayton, TN 37321 General Counsel Tennessee Valley Authority County Mayor 6A West Tower P. O. Box 156 400 West Summit Hill Drive Decatur, TN 37322 Knoxville, TN 37902 Mr. Lawrence E. Nanney, Director Mr. John C. Fornicola, Manager Division of Radiological Health Nuclear Assurance Dept. of Environment & Conservation Tennessee Valley Authority Third Floor, L and C Annex 3R Lookout Place 401 Church Street 1101 Market Street Nashville, TN 37243-1532 Chattanooga, TN 37402-2801 Mr. Larry E. Nicholson, General Manager Performance Improvement Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 67 License No. NPF-90
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Tennessee Valley Authority (the licensee) dated April 25, 2007, as supplemented by letter dated August 22, 2007, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in Title 10 Code of Federal Regulations (10 CFR) Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-90 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 67, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance, and shall be implemented no later than 45 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Thomas H. Boyce, Branch Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-90 and the Technical Specifications Date of Issuance: January 18, 2008
ATTACHMENT TO LICENSE AMENDMENT NO. 67 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace page 3 of Operating License No. NPF-90 with the attached page 3.
Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.5-2 3.5-2 3.5-10 3.5-10 4.0-1 4.0-1
(4) TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, instrument calibration, or other activity associated with radioactive apparatus or components; and (5) TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.
(1) Maximum Power Level TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 67, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15)
Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.
(4) Vehicle Bomb Control Program (Section 13.6.9 of SSER 20)
During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.
Amendment No.
SAFETY EVALUATION OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO REACTOR VESSEL INTEGRITY FOR THE REVISION OF THE NUMBER OF TRITIUM PRODUCING BURNABLE ABSORBER RODS IN THE REACTOR CORE WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390
1.0 INTRODUCTION
By letter dated April 25, 2007 (Reference 1), as supplemented by letter dated August 22, 2007 (Reference 2), the Tennessee Valley Authority (TVA, licensee) submitted a request for changes to the Technical Specifications (TSs) for Watts Bar Nuclear Plant, Unit 1 (WBN-1). Notice of this amendment was given in the Federal Register on June 5, 2007 (72 FR 31105). The August 22, 2007, letter provided clarifying information that did not change the initial proposed no significant hazards consideration determination.
The proposed amendment revises the WBN-1 TSs 3.5.1.4, AAccumulators,@ 3.5.4.3, @Refueling Water Storage Tank (RWST),@ and 4.2.1 AFuel Assemblies,@ to increase the maximum number of tritium producing burnable absorber rods (TPBARs) that can be irradiated from 240 to 400.
Although TVA is planning to irradiate only 368 TPBARs in the WBN-1 reactor core during Cycle 9, the proposed change increases the limit on TPBARs that can be irradiated to 400, and the licensee has provided an analysis to support the irradiation of up to 400 TPBARs.
2.0 BACKGROUND
The U.S. Department of Energy (DOE) has chosen TVA=s WBN-1 to produce tritium for the replenishment of the National Security Stockpile by irradiating TPBARs installed in the core.
The number of TPBARs required to be irradiated is to be identified by DOE. Based on these numbers, TVA, along with its fuel vendors, will determine the number of TPBARs to be installed and irradiated.
On September 15, 1997, the U. S. Nuclear Regulatory Commission (NRC) issued Amendment No. 8 to the WBN-1 Operating License, which authorized the irradiation of 32 Lead Test Assembly TPBARs in the WBN-1 core during operating Cycle 2.
Amendment No. 40 to the WBN-1 Operating License was issued September 23, 2002, and authorized the insertion of up to 2,304 TPBARs in the WBN-1 core. Amendment No. 40 addressed the changes needed for the production of tritium and included boron changes for the cold leg accumulators (CLAs) and RWST. The amendment stated that the number of TPBARs to be inserted in the WBN-1 core would be determined for each cycle, but would be less than or equal to 2,304.
Amendment No. 48 was issued on October 8, 2003, and authorized the irradiation of 240 TPBARs in the WBN-1 core during operating Cycle 6. Based on issues related to credit for control rod insertion during a cold leg loss-of-coolant-accident (LOCA) and sump boron, TVA noted that the number of TPBARs to be irradiated would be limited to 240 instead of the previously approved limit of 2,304.
Because the tritium permeation from TPBARs was found to be greater than expected in Cycle 6, TVA stated in a March 22, 2005, letter to NRC that the number of TPBARs irradiated in WBN-1 would remain at 240 until the permeation issue was understood and resolved, thus only 240 TPBARs were irradiated in operating Cycles 6, 7 and 8.
The DOE has requested TVA to produce higher levels of tritium in future cycles of WBN-1.
Consequently, the licensee proposes raising the maximum number of TPBARs from 240 to 400.
On the basis of post-irradiation examinations performed on the Cycle 6 TPBARs, Pacific Northwest National Laboratory (PNNL), designer of the TPBARs, has proposed changes to the TPBAR design to correct the permeation issue. TPBARs with these design changes are proposed to be irradiated in the WBN-1 core during operating Cycle 9, beginning in the spring of 2008.
TVA uses Westinghouse to perform reload safety evaluations for each reload core design to ensure that safety limits will continue to be met. The analyses performed include post-LOCA subcriticality analyses to demonstrate that subcriticality is maintained in the event of a LOCA.
Post-LOCA subcriticality margin is a function of overall core design, not simply the number of TPBARs. TVA requested that the limit on number of TPBARs be increased from 240 to 400, with the understanding that WBN-1 Cycle 9 will be analyzed using the same post-LOCA subcriticality methodology and assumptions used in Cycles 6 through 8. The core will be designed to ensure that subcriticality is maintained when the current methodology is employed.
3.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46, AAcceptance criteria for emergency core cooling systems for light-water nuclear power reactors,@ and 10 CFR Part 50, Appendix K, AECCS Evaluation Models,@ specify the requirements for the design and analysis of emergency core cooling systems (ECCS). These regulations ensure adequate core cooling following a LOCA such that specified acceptance criteria are satisfied. The specified acceptance criteria include peak clad temperature, total cladding oxidation, total hydrogen generation, maintaining a coolable core geometry and ensuring adequate long-term core cooling. The applicable acceptance criterion for this license amendment is the long-term core cooling criterion. This criterion requires that the core temperature be maintained at an acceptably low value and that decay heat be removed for the extended period of time required by the long-lived radioactive nuclides remaining in the core.
The post-LOCA long-term core cooling analysis for WBN-1 requires that the core remain subcritical considering that all boration sources are injected and mixed in the containment sump.
These boration sources include the CLAs, the RWST, and the melted ice from the ice condenser containment. The minimum boron requirement for the CLAs ensures that the reactor core will remain subcritical during the post-LOCA recirculation phase by ensuring there is
sufficient boron concentration in the containment sump following a LOCA. The minimum boron requirement for the RWST ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by reactor coolant system (RCS) cooldown.
Appendices G and H to 10 CFR Part 50, and 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock (PTS)," provide the requirements for determining the effects of neutron irradiation on the integrity of the reactor vessel. Appendix H to 10 CFR Part 50 specifies material surveillance program requirements to monitor changes in the fracture toughness properties of the reactor vessel that occur as a result of exposure of these materials to neutron irradiation. Appendix G to 10 CFR Part 50 requires that reactor vessel beltline materials have Charpy upper shelf energy (USE) values in the transverse direction for the base metal and along the weld for the weld material of no less than 75 ft-lb (102 J) initially, and must maintain Charpy USE values throughout the life of the vessel of no less than 50 ft-lb (68 J). However, in accordance with 10 CFR Part 50, Appendix G, paragraph IV.A.1.a., Charpy USE values below these criteria may be acceptable if it is demonstrated, in a manner approved by the Director, NRC Office of Nuclear Reactor Regulation, that the lower values of Charpy USE will provide margins of safety against fracture equivalent to those required by Appendix G of Section XI of the American Society of Mechanical Engineers Code. Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, provides an expanded discussion regarding the calculation of Charpy USE values. 10 CFR 50.61 establishes a PTS screening criteria that define a limiting level of neutron embrittlement beyond which plant operation cannot continue without further plant-specific evaluation.
The provisions of 10 CFR 50.36, Technical Specifications, which implements section 182a of the Atomic Energy Act, include requirements for determining the contents of TSs. These shall include surveillance requirements (SRs) relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation (LCO) will be met.
4.0 TECHNICAL EVALUATION
4.1 Technical Specifications Changes The licensee proposes to revise SR 3.5.1.4 for the Accumulators by deleting the statement,
- The number of TPBARS is limited to no more than 240 based on TVA to NRC letter dated August 18, 2003, and by revising the number of TPBARs in the table from 0-240* to 0-400.
The same changes are proposed for SR 3.5.4.3 for the RWST. Finally, in the Design Features section of the TSs, TS 4.2.1, Fuel Assemblies, is revised to state that WBN-1 is authorized to place a maximum of 400 TPBARs into the reactor.
The purpose of the SRs is to assure that the LCOs for operability of the RWST and accumulators will be maintained by periodically verifying that their boron concentrations are within the designated ranges required by the analyses supporting the number of TPBARs in the core. This has not changed and the LCOs remain in effect. The table in the LCO has been revised to reflect the new TPBAR limit. However, since the supporting analysis has been revised, the reference to the August 18, 2003, letter is no longer valid. In this letter, which was a response to an NRC staff request for additional information associated with Amendment
No. 48, TVA limited the number of TPBARs to 240 and indicated that additional analyses and/or revised boron concentrations would be required to support future increases in this number.
The current proposed amendment provides the revised information. Thus, the reference to the August 18, 2003, letter can be deleted.
The change to TS 4.2.1 updates the fuel assembly design information to reflect the increased number of TPBARs authorized.
Based on the above discussion, the NRC staff concludes that the proposed revisions to the TSs are consistent with the requirements of 10 CFR 50.36 and accurately incorporate the design change to the number of TPBARs, which is evaluated in the following sections of this safety evaluation, and are, therefore, acceptable.
The licensee also provided, for information, the proposed change to the applicable TS Bases.
The proposed change should be incorporated in accordance with the licensees TS Bases Control Program.
4.2 Post-LOCA Subcriticality Margin In the past 3 cycles, the number of TPBARs in WBN-1 was limited to 240 due, in part, to concerns related to post-LOCA subcriticality. The maximum allowable number of TPBARs is currently included in the RWST and Accumulator TSs. These TSs are related to post-LOCA subcriticality margins since the boron concentrations of ECCS water sources are important in determining the boron concentration of the water in the containment sump. The Design Features section of the TSs also includes the maximum TPBAR inventory.
Post-LOCA subcriticality analysis is a function of the detailed core design and key assumptions like the RWST and CLA boron concentrations. Depending on the core design, the number of TPBARs plays a role in determining post-LOCA subcriticality margin. However, the magnitude of the subcriticality margin is not directly determined by the number of TPBARs; that is, two different core designs can have the same number of TPBARs, but very different post-LOCA subcriticality margins.
Post-LOCA subcriticality margin, which is evaluated each cycle as part of the reload safety evaluation process, is determined by the core excess reactivity at cold conditions and by the sump boron concentration.
The core excess reactivity (i.e., the reactivity controlled by the soluble boron in the moderator) is a function of several core designs attributes - specifically, the cycle energy, the fuel design, the inventory of discrete and integral burnable absorbers, and the coolant conditions. The licensee analyzed post-LOCA subcritically conditions under normal and abnormal conditions to ensure subcriticality margin does exist and will continue to exist throughout the cycle.
The subcriticality analysis was performed using the latest versions of the ANC and PHOENIX-P computer codes combination that have TPBAR modeling capability. These have been approved for use by the NRC and are described in Section 2.4.3.1 of Reference 3.
PHOENIX-P is a lattice code used to generate fuel cross sections for ANC, which is the three-dimensional core simulator. The subcriticality calculation at cold, post-LOCA conditions is performed using ANC.
As stated above, the sump boron concentration is calculated assuming minimum RWST, CLA, and containment ice condenser boron concentrations. These minimum concentrations are specified in the plant TSs. Also, the RCS boron concentration is minimized through the assumption of peak xenon as the accident precondition. ANC is then used to calculate the HFP, peak xenon critical boron concentration at the most reactive time in life. The boron in the sump is determined based on a specified function of the peak xenon RCS boron.
The licensee reviewed the hot-leg break scenario and determined that TPBAR failure is not expected due to the low temperatures of the fuel of the TPBARs. The detail supporting this conclusion is provided in Reference 1.
The licensee also used ANC to calculate the cold critical boron concentration at post-LOCA conditions. The most reactive temperature in the range of 50 degrees F to 212 degrees F is evaluated. The moderator is assumed to be sub-cooled, and no credit is taken for the negative reactivity effect of voids. The fuel temperature is assumed to be equal to the moderator temperature, so that no credit is taken for decay heat and Doppler feedback. The resulting cold critical boron concentration is compared to the sump boron concentration. If the sump boron concentration is larger than the cold critical boron concentration, then the core is subcritical.
To address the potential for TPBAR failure, the licensee conducted post-LOCA subcriticality calculations assuming two scenarios: (1) hot leg break and (2) cold leg break. In addition, the licensee considered two types of cold leg break scenarios: (a) long term subcriticality and (b) subcriticality at the time of hot leg switch-over (HLSO). The details of these calculations are presented in Reference 1.
The licensee also considered cold leg breaks. For cold leg break LOCAs, the potential exists for boron dilution of the sump prior to HLSO. For WBN-1, HLSO occurs at 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> into the transient. At this time, switch-over to hot leg recirculation is performed to prevent the boron concentration in the core from building up to the precipitation level. Prior to HLSO, unborated steam from the core condenses in the containment, potentially reducing the boron concentration in the sump. This reduced boron concentration is assumed in the subcriticality evaluation at HLSO. Because of the potential for dilution of the sump boron, the cold leg break subcriticality assessment at HLSO is the most limiting scenario. The key assumptions for the subcriticality evaluation at HLSO are presented in Reference 1.
4.2.1 Results of the Analysis To evaluate the effect of increasing the maximum TPBAR inventory from 240 to 400, the licensee reviewed the post-LOCA subcriticality margin calculations that were performed for the past three cycles. The effect on post-LOCA subcriticality margin calculation of adding additional TPBARs, up to the maximum of 400 TPBARs, is provided in Table 1 of Reference 1. The analysis shows that the past three cycles could have accommodated the additional TPBARs with only a slight reduction in the subcriticality margin.
As stated in the licensees submittal, the core designer has options available that can increase subcriticality margin of the core through increasing the core inventory of integral fuel burnable absorber rods. As such, an explicit analysis was performed for a core design with 400 TPBARs for the upcoming Cycle 9.
The Cycle 9 core design is a modification of the Cycle 8 core design. This implies that the licensee had performed post-LOCA subcriticality calculations for each of the post-LOCA scenarios for cycle burnups up to 8000 megawatt days per metric ton of uranium (MWD/MTU).
Post-LOCA subcriticality margin is limiting early in the cycle, so that cycle burnups beyond 8000 MWD/MTU are clearly non-limiting.
ANC is used to calculate the precondition boron concentrations at the peak xenon condition at several different burnup steps. The resulting values can then be used to determine the sump boron concentrations.
Cold critical boron concentrations were also calculated assuming no xenon. The coolant conditions are atmospheric pressure and the most reactive temperature between 50 degrees Fahrenheit (°F) and 212 °F. For the HLSO subcriticality assessment, a conservative xenon credit is utilized, since HLSO occurs 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> into the transient, at which time a significant xenon inventory would remain in the core. For a HLSO time of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, the conservative xenon credit assumed is 210 parts per million (ppm). A detailed description supporting the assumption used in this calculation is contained in the Aresults@ section of the Reference 1. The licensee stated that the minimum xenon credit values conservatively assume a reactor trip and a 15-hour power ramp to full power prior to the LOCA. If pre-trip power history is consistent with the assumptions that maximize sump dilution (i.e., most reactive time-in-life, continuous full power operation),
xenon credit would be much higher.
The subcriticality margin is calculated by subtracting the calculated critical boron concentration from the sump boron concentration. Tables 2, 3, 4, and 5 of Reference 1 provide the results of the post-LOCA subcriticality analysis for hot and cold leg breaks.
As the tables show, beginning of life (BOL) (150 MWD/MTU) is the most limiting time in life for each scenario. Also, the licensee pointed out that the HLSO assessment is the most limiting scenario with a minimum margin of 116 ppm at BOL.
A review of the tables indicates that the modified Cycle 8 core has slightly less excess reactivity than the excess reactivity assumed in Table 1 (1813 ppm critical boron vs. 1828 ppm critical boron at BOL cold conditions for the modified Cycle 8 core and the actual Cycle 8 core, respectively).
Also, the subcriticality margin values in Tables 4 and 5 show that, at 150 MWD/MTU, the worth of the Li-6 lost due to TPBAR failure is 52 ppm (168 ppm B 116 ppm). This is equivalent to 0.13 ppm per TPBAR, which is consistent with the value assumed in Table 1 for Cycle 8. This supports the reasonableness of the Table 1 estimates for Cycles 6 and 7.
The staff concurs with the licensees results, as presented in Reference 1, that adequate subcriticality margin has been demonstrated for a core design with 400 TPBARs. Additionally, the methods described in this submittal are adequate to assess the cycle-specific post-LOCA subcriticality margin for future WBN-1 core designs.
4.3 Reactor Vessel Integrity The neutron fluence is the main parameter used to characterize the extent of embrittlement expected in the reactor vessel material. The proposed increase in the number of TPBARs from 240 to 400 is well below the 2,304 TPBARs approved in the staff's safety evaluation dated September 23, 2002. Therefore, the projected neutron fluence still remains valid, and the reactor vessel pressure-temperature limit curves and material reference temperature (RTPTS) values evaluated for the end of license neutron fluence using the PTS screening criteria remain valid for the end of life conditions.
As stated in the staff's safety evaluation dated September 23, 2002, WBN-1 license condition C.(5) requiring TVA to perform fracture toughness (J-R curve) testing on specimens removed from surveillance capsules W and X is sufficient to ensure that the WBN-1 reactor vessel complies with the Charpy USE requirements of Appendix G to 10 CFR Part 50 through the end of its license. It should be noted that this license condition was initially included because the staff conditioned its acceptance of the TVA's equivalent margins analysis in the NRC's Supplement No. 14 to NUREG-0847, "Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Units 1 and 2," dated December 1994.
The NRC staff finds that the increase in the number of TPBARs from 240 to 400 at WBN-1 does not change the analysis related to the reactor vessel integrity and that the requirements of the staffs safety evaluation dated September 23, 2002, related to the reactor vessel integrity analysis remain valid.
4.4 Structural Changes As previously noted, PNNL, the designer of the TPBARs, proposed changes to the TPBAR design to correct the permeation issue, and TPBARs with these design changes are proposed to be irradiated in the WBN-1 core starting with operating Cycle 9. The changes are primarily related to the design of internal components.
In its safety evaluation for Amendment No. 40 to the WBN-1 Operating License, which authorized the insertion of up to 2,304 TPBARs in the WBN-1 core, the NRC staff did not perform a detailed structural evaluation. Rather, it based its acceptance of the structural design on review of the DOE/TVA Interagency Agreement, which provides a means for imposing TVA requirements for safety-related components directly on DOEs TPBAR suppliers. This insures that TPBAR design, procurement and fabrication will be performed in accordance with a quality assurance (QA) program that complies with 10 CFR Part 50, Appendix B and NRC Regulatory Guide 1.28, Quality Assurance Program Requirements (Design and Construction).
In its August 22, 2007, response to a staff request for additional information, the licensee stated that the controls used in the design, fabrication and procurement of the redesigned TPBARs and TPBAR components are the same as those used in the original design.
Therefore, the NRC staff concludes that the changes to the structural design of the TPBARs will be made in accordance with applicable NRC regulatory procurement and QA requirements, and are acceptable.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, an official of the Tennessee Bureau of Radiological Health was notified of the proposed issuance of the amendment. The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments 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, and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (72 FR 31105). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public. Therefore, on the basis of the above review and justification, the staff concludes that the requests proposed in TVAs April 25, 2007 submittal are acceptable.
8.0 REFERENCES
- 1. Letter from J. D. Smith, TVA, to the NRC, Watts Bar Nuclear Plant (WBN) Unit 1 -
Technical Specification Change 07-01, Revision of Number of Tritium Producing Burnable Absorber Rods (TPBARS) in the Reactor Core, dated April 25, 2007.
- 2. Letter from J. D. Smith, TVA to the NRC, Watts Bar Nuclear Plant (WBN) Unit 1 -
Technical Specification Change 07-01, Revision of Number of Tritium Producing Burnable Absorber Rods (TPBARS) in the Reactor Core - Response to Telecon Questions, dated August 22, 2007.
- 3. NDP-00-0344, Rev. 1, Revision 1, AImplementation and Utilization of Tritium Producing Burnable Absorber Rods (TPBARS) in Watts Bar Unit 1,@ Westinghouse Electric Company, July 2001. (This document was Enclosure 4 of TVA=s letter to NRC, dated August 20, 2001, AWatts Bar Nuclear Plant (WBN) - Unit 1 - Revision of Boron Concentration Limits, Reactor Core Limitations for Tritium Production Cores (TPCs) -
Technical Specification (TS) Change No. TVA-WBN-TS-00-015.@)
Principle Contributors: Anthony Attard John Honcharik Brendan Moroney Date: January 18, 2008