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MONTHYEARML0808703492008-03-27027 March 2008 Technical Specifications (TS) Change - TS-07-18 - Revision of the Allowable Value for the Containment Purge Exhaust Radiation Monitors - Limiting Condition for Operation (LCO) 3.3.6, Containment Vent Isolation Instrumentation. Project stage: Request ML0821304242008-08-0101 August 2008 Request for Additional Information, Allowable Value for Containment Purge Exhaust Radiation Monitors Project stage: RAI ML0827300872008-09-26026 September 2008 Response to Request for Additional Information Regarding Allowable Value for Containment Purge Exhaust Radiation Monitors Project stage: Response to RAI ML0833803692009-01-0808 January 2009 Issuance of Amendment Regarding the Allowable Value for the Containment Purge Exhaust Radiation Monitors Project stage: Approval 2008-08-01
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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-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARCNL-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) 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-23-045, 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) 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-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu CNL-23-015, Expedited Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-22-08)2023-02-27027 February 2023 Expedited Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-22-08) CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-071, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-07-13013 July 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-001, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-04-0404 April 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) CNL-22-003, Application to Modify the Allowable Value for Watts Bar Nuclear Plant, Unit 1 Technical Specification Table 3.3.2-1, Function 6.e(1) (WBN-TS-21-010)2022-02-17017 February 2022 Application to Modify the Allowable Value for Watts Bar Nuclear Plant, Unit 1 Technical Specification Table 3.3.2-1, Function 6.e(1) (WBN-TS-21-010) CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .2021-12-0909 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . CNL-21-062, Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board Cleaning (WBN-TS-19-019)2021-09-29029 September 2021 Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board Cleaning (WBN-TS-19-019) ML21202A2242021-07-0202 July 2021 Tennessee Valley Authority (TVA)- Watts Bar Nuclear Plant (WBN)- NPDES Permit No. TN0020168-Application Request for Permit Renewal CNL-21-038, Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (W2021-06-0101 June 2021 Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (WBN CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN82021-04-29029 April 2021 Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89- CNL-21-013, Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (WBN-TS-20-06)2021-03-11011 March 2021 Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (WBN-TS-20-06) CNL-21-015, Expedited Application to Modify Watts Bar Nuclear Plant, Unit 1 Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening of the Auxiliary Building Secondary Containment Enclosure as2021-03-0303 March 2021 Expedited Application to Modify Watts Bar Nuclear Plant, Unit 1 Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening of the Auxiliary Building Secondary Containment Enclosure as N CNL-21-016, License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05)2021-03-0202 March 2021 License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05) CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID2021-01-26026 January 2021 Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID L CNL-20-104, Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for (WBN TS-391-20-024)2020-12-23023 December 2020 Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for (WBN TS-391-20-024) CNL-20-093, Supplement to Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 'Containment Leakage Rate Testing Program' (WBN-TS-19-01)2020-12-15015 December 2020 Supplement to Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 'Containment Leakage Rate Testing Program' (WBN-TS-19-01) CNL-20-087, Non-Voluntary Application to Modify Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications Surveillance Requirement 3.6.15.4, Shield Building, (WBN-TS-20-017)2020-12-15015 December 2020 Non-Voluntary Application to Modify Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications Surveillance Requirement 3.6.15.4, Shield Building, (WBN-TS-20-017) CNL-20-078, Supplement to Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sa2020-10-13013 October 2020 Supplement to Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Samp CNL-20-006, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 Containment Leakage Rate Testing Program (WBN-TS-19-01)2020-10-0202 October 2020 Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 Containment Leakage Rate Testing Program (WBN-TS-19-01) CNL-20-058, Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27)2020-08-27027 August 2020 Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27) CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016)2020-08-14014 August 2020 License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance2020-07-31031 July 2020 Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re CNL-20-063, Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-07-27027 July 2020 Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-20-053, Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-392020-07-17017 July 2020 Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-390- CNL-20-040, License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07)2020-07-17017 July 2020 License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07) CNL-20-016, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23)2020-06-22022 June 2020 Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) CNL-20-012, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-18-16)2020-05-19019 May 2020 Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-18-16) CNL-20-005, License Amendment Request to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, (WBN-TS-20-02)2020-04-0303 April 2020 License Amendment Request to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, (WBN-TS-20-02) CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific2020-03-0202 March 2020 Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specificat CNL-19-084, Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program...2020-01-17017 January 2020 Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program... CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology2020-01-17017 January 2020 Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology CNL-20-004, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01)2020-01-17017 January 2020 Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) CNL-19-110, Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10)2019-12-17017 December 2019 Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10) CNL-19-077, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications 3.6.15, Shield Building, (WBN-TS-19-10)2019-12-0606 December 2019 Application to Modify Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications 3.6.15, Shield Building, (WBN-TS-19-10) CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)2019-09-30030 September 2019 Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13) CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)2019-08-29029 August 2019 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) CNL-19-038, License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)2019-06-0707 June 2019 License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02) CNL-19-014, Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07)2019-02-0707 February 2019 Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07) CNL-18-118, Application to Revise Technical Specifications Regarding DC Electrical Systems TStf-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 (WBN-TS-18-09)2018-11-29029 November 2018 Application to Revise Technical Specifications Regarding DC Electrical Systems TStf-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 (WBN-TS-18-09) CNL-18-068, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24)2018-11-29029 November 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24) CNL-18-119, Application to Revise Watt Bar Nuclear Plant, Units 1 & 2, Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9, Regarding Electrical Power Systems (WBN-TS-1808)2018-11-26026 November 2018 Application to Revise Watt Bar Nuclear Plant, Units 1 & 2, Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9, Regarding Electrical Power Systems (WBN-TS-1808) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays 2023-09-20
[Table view] Category:Technical Specifications
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 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) 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) 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 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 CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) WBL-22-017, Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2022-03-22022 March 2022 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level 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 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 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 ML20226A4442020-10-21021 October 2020 Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate ML20273A0432020-09-29029 September 2020 Plants Unit 1 and 2 - Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual ML20156A0182020-08-10010 August 2020 Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific2020-03-0202 March 2020 Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specificat 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 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 CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)2019-09-30030 September 2019 Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13) CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)2019-08-29029 August 2019 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19112A0042019-07-25025 July 2019 Issuance of Amendment Nos. 127 and 30 Regarding the Use of Optimized Zirlo Fuel Rod Cladding ML19098A7742019-06-0707 June 2019 Issuance of Amendments Regarding Technical Specifications Changes Pertaining to 120-Volt Alternating Current Vital Buses ML18255A1562018-10-30030 October 2018 Issuance of Amendment to Modify Technical Specification 3.3.1 Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure ML18079A0292018-06-26026 June 2018 Issuance of Amendments Regarding Adoption of TSTF-547, Clarification of Rod Position Requirements (CAC Nos. MF8912and MF8913; EPID L-2016-LLA-0034) ML17311A7862017-12-0707 December 2017 Issuance of Amendment Regarding Ventilation Filter Testing Program (CAC No. MF9584; EPID L-2017-LLA-0207) ML17215A2432017-10-0202 October 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566) CNL-17-029, Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources2017-03-0606 March 2017 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources ML16343A8142017-01-0505 January 2017 Issuance of Amendment Regarding One-Time Extension of Intervals for Surveillance Requirements 3.6.11.2 and 3.6.11.3 CNL-16-164, Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024)2016-10-17017 October 2016 Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024) NL-16-164, Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024)2016-10-17017 October 2016 Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications to Extend Surveillance Requirement Intervals for AC Sources (WBN-TS-16-024) ML16159A0572016-07-29029 July 2016 Issuance of Amendment Regarding Revised Technical Specification 4.2.1 Fuel Assemblies to Increase the Maximum Number of Tritium Producing Burnable Absorber Rods CNL-16-047, Response to Request for Additional Information Regarding Request to Use F* Steam Generator Alternate Repair Criteria2016-05-0404 May 2016 Response to Request for Additional Information Regarding Request to Use F* Steam Generator Alternate Repair Criteria ML15344A3182015-12-23023 December 2015 Issuance of Amendment Regarding Fire Protection License Conditions ML15348A1122015-12-14014 December 2015 Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program ML15251A5872015-10-22022 October 2015 Issuance of Facility Operating License No. NPF-96 Watts Bar Nuclear Plant, Unit 2 ML15301A1402015-10-22022 October 2015 Current Facility Operating License NPF-96, Tech Specs, Revised 11/08/2017 ML15275A0422015-10-20020 October 2015 Issuance of Amendment Regarding Application to Revise Technical Specifications for Component Cooling Water and Essential Raw Cooling Water to Support Dual Unit Operation ML15230A1552015-09-17017 September 2015 Issuance of Amendment Regarding Modification to Technical Specification 3.8.1 Regarding Diesel Generator Steady-State Frequency NL-15-177, Watts Bar, Unit 2, Submittal of Replacement Pages for Developmental and Final Revision J of the Technical Specification & Technical Specification Bases, and Developmental and Final Revision E of Technical Requirements Manual & Technical Ma2015-09-0404 September 2015 Watts Bar, Unit 2, Submittal of Replacement Pages for Developmental and Final Revision J of the Technical Specification & Technical Specification Bases, and Developmental and Final Revision E of Technical Requirements Manual & Technical Man 2024-01-09
[Table view] |
Text
March 27, 2008 TVA-WBN-TS-07-18 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Gentlemen:
In the Matter of the ) Docket No. 50-390 Tennessee Valley Authority ) WATTS BAR NUCLEAR PLANT (WBN) - UNIT 1 - TECHNICAL SPECIFICATIONS (TS)
CHANGE - TS-07 REVISION OF THE ALLOWABLE VALUE FOR THE CONTAINMENT
PURGE EXHAUST RADIATION MONITORS - LIMITING CONDITION FOR OPERATION (LCO) 3.3.6, "CONTAINMENT VENT ISOLATION INSTRUMENTATION" Pursuant to 10 CFR 50.90, Tennessee Valley Authority (TVA) is submitting a request for a TS change (TS-07-18) to License NPF-90 for WBN. The proposed TS change revises the allowable value listed for Function 3, "Containment Purge Exhaust Radiation Monitors," in Table
3.3.6-1, "Containment Vent Isolation Instrumentation," of LCO 3.3.6. The Containment Purge
exhaust radiation monitors (1-RE-90-130-A and 1-RE-90-131-B) initiate containment vent
isolation to mitigate the potential release of radioactive effluents via this flow path following a
postulated Small Break Loss of Coolant Accident (SBLOCA).
The current allowable value is appropriate when the containment purge exhaust filters are
credited. However, that value was deemed nonconservative in Modes 1 through 4 operation
because the containment purge exhaust filters are not credited in the WBN design and licensing
basis and are not required to be operational in those operating modes by the WBN Technical
Specifications. Administrative controls hav e been implemented to impose a more conservative allowable value and setpoint that does not credit the containment purge exhaust filters. WBN
procedure 1-ODI-90-15, "Containment Purge Release" Revision 26 has been implemented with
precautions and specific notes to restrict the setpoint for these monitors. This setpoint has been
established through approved instrumentation accuracy calculations for these monitors to
ensure the proposed allowable value will not be exceeded. This administratively controlled
allowable value and setpoint will ensure compliance with the WBN U.S. Nuclear Regulatory Commission Page 2 March 27, 2008 design and licensing basis during the processing of this request. Review of past setpoints for this function concluded that the settings were always lower than the proposed allowable value
and the associated setpoint. The setpoint for this function has been maintained well below the
proposed allowable value.
TVA has determined that there are no significant hazards considerations associated with the
proposed change and that the TS change qualifies for categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). Additionally, in accordance with 10
CFR 50.91(b)(1), TVA is sending a copy of this letter and enclosures to the Tennessee State
Department of Public Health.
TVA requests approval of this TS change by the beginning of the Cycle 9 refueling outage which
is currently scheduled to begin in the fall of 2009. TVA intends to implement the revised TS
within 30 days of NRC approval.
There are no regulatory commitments associated with this submittal.
If you have any questions about this change, please contact me at 423-365-1824.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 27 th day of March, 2008.
Sincerely, Original signed by M. K. Brandon Manager, Site Licensing and Industry Affairs
Enclosure:
Evaluation of the Proposed Change cc: See page 3 U.S. Nuclear Regulatory Commission Page 3 March 27, 2008 Enclosure cc (Enclosure): NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 ATTN: Margaret H. Chernoff, Senior Project Manager U.S. Nuclear Regulatory Commission Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MS O-8 H4-A Washington, DC 20555-0001 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. Lawrence E. Nanny, Director Division of Radiological Health 3rd Floor L & C Annex 401 Church Street Nashville, Tennessee 37243
ENCLOSURE EVALUATION OF THE PROPOSED CHANGE
Subject:
Watts Bar Nuclear Plant (WBN) Unit 1 - Technical Specifications (TS) Change -
TS-07 Revision of the Allowable Value for the Containment Purge Exhaust Radiation Monitors - Limiting Condition for Operation (LCO) 3.3.6, "Containment
Vent Isolation Instrumentation."
1.0
SUMMARY
DESCRIPTION This evaluation supports a request to amend Operating License NPF-90 for WBN Unit 1.
The proposed TS change revises the allowable value listed for Function 3, "Containment
Purge Exhaust Radiation Monitors," in Table 3.3.6-1, "Containment Vent Isolation
Instrumentation," of LCO 3.3.6, during Modes 1 through 4. The current allowable value
remains acceptable during movement of irradiated fuel assemblies within containment.
The Containment Purge exhaust radiation monitors (1-RE-90-130-A and 1-RE-90-131-B)
initiate containment vent isolation to mitigate the potential release of radioactive effluents
via this flow path following a postulated Small Break Loss of Coolant Accident (SBLOCA). The isolation of this flow path serves to limit radiological consequences of
the design basis SBLOCA to well within the limits of 10 CFR 100, "Reactor Site Criteria."
These monitors and the associated TS allowable value are not used to protect the
nuclear fuel or the Reactor Coolant System safety barriers; therefore, the allowable value revised by this change is not a 10 CFR 50.36, "Technical Specifications," limiting
safety system setting.
The current allowable value was determined to be non-conservative for operating Modes
1 through 4, and this condition has been documented in TVA's corrective action
program. The allowable value was determined to be non-conservative because the
basis for the specified value inappropriately credited the containment purge exhaust
filters, when the TS LCO 3.9.8 only requires these filters during movement of irradiated
fuel assemblies within containment. Administrative controls have been implemented to
impose a more conservative allowable value that does not credit the containment purge
exhaust filters. This administratively controlled allowable value will ensure compliance
with the WBN's design and licensing basis during the processing of this request.
2.0 DETAILED DESCRIPTION The Containment Purge exhaust radiation monitors are gaseous effluent monitors which continuously monitor the radioactivity in the exhaust air from the containment
atmosphere as required in 10 CFR 50, Appendix A, GDC 60 and 64. The two redundant
safety-related monitors perform a primary safety function for mitigation of the offsite dose
consequences for a limited break size spectrum of SBLOCA events. A high radiation signal from either noble gas monitor automatically generates a Containment Vent
Isolation (CVI) signal which in turn shuts down the Reactor Building Purge Ventilation
System (RBPVS) fans and isolates the syst em by closing its respective dampers and butterfly valves. The automatic isolation func tion of these monitors is a primary safety function, since it mitigates the potential release of radioactive material to the
environment following a postulated design basis event which satisfies the requirements E1-1 described in 10 CFR 100. Note for the design basis large break LOCA, a safety injection signal is credited for generation of the CVI signal.
The analytical limit (activity level in the flow stream) established for the Containment
Purge exhaust radiation monitors is based on isolating the Containment Purge exhaust
before reaching 10 percent of the exclusion area boundary dose limit for a SBLOCA. In
establishing the analytical limit, the Containment Purge exhaust filters were credited.
The Containment Purge exhaust radiation monitor allowable value in TS Table 3.3.6-1 is based on the analytical limit. Since the analytical limit and allowable value credits the
Containment Purge exhaust filters for accident mitigation, filter testing in accordance
with R.G.1.52 is required. Based on the preceding, TVA documented in its corrective
action program that there is no Surveillanc e Requirement (SR) for Containment Purge exhaust filter testing in Modes 1 to 4 even though the allowable value specified in TS
Table 3.3.6-1 Item 3 for the Containment Purge exhaust radiation monitors takes credit
for purge exhaust filtration during Modes 1 to 4.
In order to resolve this condition, the Containment Purge exhaust radiation monitor analytical limit for Modes 1 to 4 was conservatively reduced to a value that will initiate a
CVI to control releases to well within 10 CFR 100 limits without the need to take credit
for the Containment Purge exhaust filters. No change was required during movement of
irradiated fuel assemblies within containment, as TS LCO 3.9.8 requires operability of
the Containment Purge exhaust filters during such movement. This change resulted in
keeping the analytical limit of 1.87 E-01 Ci/cc (Containment Purge exhaust filters credited) only for movement of irradiated fuel assemblies within containment, and using
a limit of 4.3 E-02 Ci/cc (Containment Purge exhaust filters not credited) for Modes 1 to
- 4. Based on this modification to analytical limits, the Containment Purge exhaust
radiation monitor allowable value in TS Table 3.3.6-1 is being revised to be consistent
with the new analytical limit. The proposed revision retains the current allowable value
of less than or equal to 8.41E-02 Ci/cc (8.41E+04 cpm) during movement of irradiated fuel assemblies within containment, and adds a new allowable value of less than or
equal to 2.8 E-02 Ci/cc (2.8E+04 cpm) in Modes 1 to 4.
3.0 TECHNICAL EVALUATION
Containment Purge exhaust radiation monitor analytical limit and allowable value ensures that the monitor will isolate the C ontainment Purge exhaust to limit the offsite radiological consequences of a postulated SBLOCA. The analytical limit for the monitor
is conservatively determined such that the monitor will isolate the Containment Purge
exhaust before exceeding 10 percent of the offsite dose limits for a SBLOCA. In
establishing the analytical limit, the purge exhaust filters may or may not be credited. If
the purge exhaust filters are credited in establishing the monitor analytical limit, a higher
activity concentration can be allowed in the flow stream upstream of the Containment Purge exhaust filters since the filters will remove a significant percentage of the activity
in the exhaust. If the filters are not credited, the allowable activity concentration in the
flow stream upstream of the filters is reduc ed since none of the activity is assumed to be removed by the exhaust filter.
The allowable value is a limiting value for the setpoint. The allowable value is more conservative than the analytical limit and ensures that sufficient margin exists to account for instrument uncertainties that either are not present or are not measurable during
testing (i.e., unmeasurables). The actual setpoint is more conservative than the E1-2 allowable value, and is chosen to ensure that actuation will occur prior to exceeding the analytical limit.
For the proposed amendment, the allowable value for the trip setpoint for the containment ventilation isolation signal in itiated by the Containment Purge exhaust radiation monitors (loops 1-R-90-130-A and 1-R-90-131-B) is being decreased from
8.41E-02 Ci/cc to 2.8E-02 Ci/cc for Modes 1 to 4. This is necessary due to the lower analytical limit required if the Containment Purge exhaust filters are not credited with
decreasing the released concentration. The analytical limit used to establish the
allowable value proposed in the TS change was calculated in WBN design calculation
WBNAPS3079, "Safety Limit for the Containment Purge Exhaust Monitors." This is the
same calculation used to calculate the analytical limit used to establish the current
allowable value. This same calculation was used to determine the analytical limits for
both crediting and not crediting the Containment Purge exhaust filters.
The methodology used to determine the allowable value (AV) is a conservative variation of Method 3 of ISA-RP67.04.02-2000, "Methodologies for the Determination of Setpoints
for Nuclear Safety Related Instrumentation." This methodology is defined in TVA's
Technical Instruction EEB-TI-28, Setpoint Calculations.
The high AV is determined based on the following equation:
AV < (AL - (Adbe-Anf))
Adbe = design basis accident accuracy Anf = normal measurable accuracy.
The low AV is determined by the following equation:
AV > (SP + Anf)
SP = the setpoint.
The AV specified in TS Table 3.3.6-1 is set half way between these two values. This assures that there is additional margin for non-statistical unmeasurables. The
Containment Purge exhaust radiation monitors initiate containment vent isolation to assure that releases are well within 10 CFR 100 limits. Because the monitors are not
used to protect the reactor fuel or the Reactor Coolant System safety barriers, the
allowable value specified in the TS for this device is not a 10 CFR 50.36 limiting safety system setting.
Only the AV is provided in TS Table 3.3.6-1 because the actual setpoint is conservatively determined by WBN's Chemistry staff in accordance with the Offsite Dose
Calculation Manual (ODCM) prior to every pur ge of containment. The limiting (highest) setpoint, as well as instrument loop and component accuracies, and the AV are
determined by instrument accuracy calcul ation 1-RE-90-130, "Demonstrated Accuracy Calculation for Containment Building Purge Air Exhaust Monitors." The setpoint and AV
are based on the AL provided in design calculation WBNAPS3079. In addition to the
conservatisms of the AV determination as discussed above, the setpoint determination is
conservative in that it assumes all gaseous radiation is from the isotope to which the
monitor is least sensitive, and additionally assumes the monitor is no more accurate than
the required accuracy, both of which work to force the setpoint lower. WBN's Chemistry staff determines the setpoint for the release based on containment samples in E1-3 accordance with procedure 1-ODI-90-15, "Containment Purge Release." WBN's Maintenance staff performs setpoint calibration in accordance with 1-SI-90-5, "92 Day
Channel Operational Test of the General Atomic Containment Purge Air Exhaust Radiation Monitor Loop 1-LPR-90-130," and 1-SI-90-7, "92 Day Channel Operational
Test of the General Atomic Containment Purge Air Exhaust Radiation Monitor Loop 1-LPR-90-131," which refer to setpoint and scaling documents 1-R-90-130 and
1-R-90-131. These setpoint and scaling documents provide the limiting setpoint value
determined in calculation 1-RE-90-130. WBN procedure 1-ODI-90-15 contains
restrictions that will not allow the setpoint for containment purge activities to be adjusted
higher than the maximum allowable setpoint as determined in calculation 1-RE-90-130.
Eighteen month channel calibrations 1-SI-90-6, "18 Month Channel Calibration (Source Calibration) of the General Atomic Contai nment Purge Air Exhaust Radiation Monitor Loop 1-LPR-90-130," and 1-SI-90-8, "18 Month Channel Calibration (Source Calibration) of the General Atomic Containment Purge Air Exhaust Radiation Monitor Loop 1-LPR-
90-131," assure that the monitor instrumentation and setpoints are within the required
limits and accuracies. These calibration procedures test the entire loop through
containment ventilation isolation. The procedures include performance calibration of the
radiation ratemeter to a known radiation source, calibration of the bistable setpoint (by
reference to procedures 1-SI-90-6 and 1-SI-90-8), and testing the ratemeter bistable
interlocks with alarms, annunciation, and containment ventilation isolation. Channel
operational tests, performed every 92 days by 1-SI-90-5 and 1-SI-90-7, include
verification that the bistable which initiates containment ventilation isolation is within its
as-left calibration accuracy. Any tested compliance component found outside of the as-left calibration accuracy is reset prior to exiting the procedure.
In summary, the allowable value for the Containment Purge exhaust radiation monitors listed in TS Table 3.3.6-1 is being revised to be consistent with the analytical limit that does not credit the Containment Purge exhaust filters for Modes 1 to 4, and to keep the
analytical limit that does credit the Containment Purge exhaust filters during movement
of irradiated fuel assemblies within containment. The revised analytical limit and
allowable value will ensure the Containment Pu rge exhaust radiation monitors will isolate the Containment Purge exhaust consistent with the plant's design and licensing basis for
mitigating the consequences of SBLOCA to well within the dose limits of 10 CFR 100.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria Containment Purge exhaust radiation monitor analytical limit and allowable value ensures that the monitor will isolate t he Containment Purge exhaust in the event
of a small break loss-of-coolant accident (SBLOCA). For the design basis large
break LOCA, this function is accomplished by a Safety Injection initiation. The
analytical limit for the monitor is conservatively set such that the monitor will
isolate the Containment Purge exhaust to limit the associated offsite radiological
consequences to well within the limits of 10 CFR 100 for the design basis
SBLOCA event. Two analytical limits have been established by calculation, depending on whether the purge exhaust filters are or are not credited. If the
purge exhaust filters are credited in establishing the monitor analytical limit, a
higher activity concentration can be allowed in the flow stream upstream of the
Containment Purge exhaust filters since the filters will remove a significant
percentage of the activity in the exhaust. If the filters are not credited, the E1-4 allowable activity concentration in the flow stream upstream of the filters is reduced since none of the activity is assumed to be removed. This TS change
requests the revision of an allowable value in the TS to a value that does not
credit the exhaust filters for Modes 1 to 4 operations, while maintaining the
existing allowable value for movement of irradiated fuel assemblies within
containment.
4.2 Significant Hazards Consideration The proposed Technical Specification (TS) change revises the allowable value listed for Function 3, "Containment Purge Exhaust Radiation Monitors," in Table
3.3.6-1, "Containment Vent Isolation Instrumentation," of LCO 3.3.6. The
Containment Purge exhaust radiation monitors (1-RE-90-130-A and
1-RE-90-131-B) initiate containment vent isolation to mitigate the potential
release of radioactive effluents via this flow path following a postulated Small
Break Loss of Coolant Accident (SBLOCA). The proposed change corrects a
non-conservative allowable value in Modes 1 to 4 where the Containment Purge
exhaust filters were inappropriately credited for the mitigation of the radiological
consequences associated with a SBLOCA. The proposed TS allowable value
ensures the monitors will isolate the Containment Purge exhaust and ensures the
consequences are well within the applicable regulatory limits. This change does
not affect any accident doses reported in the FSAR.
TVA has evaluated whether or not a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in
10 CFR 50.92, "Issuance of Amendment," as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change is associated with radiation effluent monitoring and isolation of Containment Purge exhaust flow in the event of a design
basis SBLOCA. The change is not associated with equipment or
processes which can initiate a design basis accident. Consequently, this
change does not affect the probability of an accident previously
evaluated.
The revised purge exhaust monitor allowable value will ensure the monitors isolate the purge exhaust and will limit the offsite doses
associated with a SBLOCA to well within the limits of 10 CFR 100. This
change serves to ensure the consequences of an accident previously
evaluated remain bounded by the plant's current licensing basis.
Therefore, the consequences of accidents previously evaluated are not
increased by this change.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
E1-5 Response: No.
The proposed change is associated with radiation effluent monitoring and isolation of Containment Purge exhaust flow in the event of a design basis SBLOCA. The change is not associated with equipment or
processes which can initiate a design basis accident. The change does
not introduce new accident initiators or physical changes in plant
equipment.
Therefore, the proposed change does not create the possibility of a new or different kind of accident fr om any previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed change involves a conservative change in the Containment Purge exhaust radiation monitor allowable value in TS Table 3.3.6-1. The
new allowable value reflects a change in the monitor analytical limit which
does not assume credit for the Containment Purge exhaust filters. The
proposed allowable value will ensure the monitors will isolate the purge
exhaust as assumed in the existing design basis SBLOCA analysis.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, TVA concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10
CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration"
is justified.
4.3 Conclusions
In conclusion, based on the considerations discussed above, (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 the amendment will not be inimical to the common defense and
security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted
area, as defined in 10 CFR 20, or would change an inspection or surveillance
requirement. However, the proposed amendment does not involve (i) a significant
hazards consideration, (ii) a significant change in the types or significant 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
amendment meets 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 E1-6 statement or environmental assessment need be prepared in connection with the proposed amendment.
E1-7
6.0 REFERENCES
None ATTACHMENTS
- 1. Technical Specifications Page Markups E1-8 A1-1 ATTACHMENT 1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES (MARK-UP)
I. AFFECTED PAGE LIST Unit 1 3.3-56 II. MARKED PAGES See attached.
Containment Vent Isolation Instrumentation 3.3.6 Watts Bar-Unit 1 3.3-56 A1-2 Table 3.3.6-1 (page 1 of 1)
Containment Vent Isol ation Instrumentation FUNCTION REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Manual Initiation 2 SR 3.3.6.6 NA 2. Automatic Actuation Logic and Actuation Relays
- 3. Containment Purge Exhaust Radiation Monitors 2 trains 2 SR 3.3.6.2 SR 3.3.6.3 SR 3.3.6.5 SR 3.3.6.1 SR 3.3.6.4 SR 3.3.6.7 NA 8.41E-02 Ci/cc (a) (8.41E+04 cpm) 2.8E-02 Ci/cc(b) (2.8E+04 cpm)
- 4. Safety Injection Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 1, for all initiation functions and requirements.
(a) During movement of irradiated fuel assemblies within containment (b) Modes 1, 2, 3, and 4