ML13175A136
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| ML13175A136 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/08/2012 |
| From: | Piplica N C Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 2-PTI-085-06, Rev 0 | |
| Download: ML13175A136 (148) | |
Similar Documents at Watts Bar | |
|---|---|
Category:Graphics incl Charts and Tables
MONTHYEARWBL-23-013, 10 CFR 50.46 Annual Report for 20222023-03-29029 March 2023
[Table view]10 CFR 50.46 Annual Report for 2022 WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted 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) ML18022A3642018-01-19019 January 2018 Survey Codes_Twra CNL-17-141, Tennessee Valley Authority - Anchor Darling Double Disc Gate Valve Information and Status2017-12-28028 December 2017 Tennessee Valley Authority - Anchor Darling Double Disc Gate Valve Information and Status ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports CNL-15-213, Compliance with Three Mile Island (TMI) Action Plan Requirements for an Operating License2015-10-0707 October 2015 Compliance with Three Mile Island (TMI) Action Plan Requirements for an Operating License ML15238B6672015-09-0303 September 2015 MSFHI Public Table ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T ML13255A3152013-08-14014 August 2013 Final Safety Analysis Report (Fsar), Amendment 110, Table 6.2.4-1 Containment Penetrations and Barriers - Page 1 of 64 - Page 64 of 64 ML13175A1352013-03-0505 March 2013 2-PTI-092-03, Revision 0, Nuclear Instrumentation Source Range Noise Checks During Hot Functional Testing. ML13175A1362012-11-0808 November 2012 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification. ML13175A1342012-11-0101 November 2012 2-PTI-082-02, Revision 0, Rod Control - Non Hft. ML13175A1332012-10-22022 October 2012 2-PTI-085-01, Revision 0, Rod Control Functional Test. ML12157A3042012-07-24024 July 2012 SECY-12-0103 - Enclosure 1 - Statistical Status Report - Sixth Report on the Status of Reactivation of Construction and Licensing for Watts Bar Nuclear Plant, Unit 2 ML12157A4612012-07-24024 July 2012 SECY-12-0103 - Enclosure 2 - Future Activities for Watts Bar Unit 2, Reactivation Project Plan ML11203A0052011-07-21021 July 2011 SECY-11-0102 - Enclosure 2 - Chart of Future Activities - Fourth Report on Status of Reactivation of Construction and Licensing for Watts Bar Nuclear Plant Unit 2 ML11178A1852011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 15.0, Accident Analyses, Through Table 15A-2 Accident Atmospheric Dilution Factors (sec/m3) ML11178A1822011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Content, Section 12.0, Radiation Protection, Through Appendix 12A - Radiation Protection Features for the Tritium Production Program ML11178A1842011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 14.0, Initial Test Program Through Figures 14.2-2 Power Ascension Test Schedule ML11178A1812011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 11.0, Through Table 11A-2 Tritium Release for 1972 from Westinghouse Designed Operating Reactors ML11178A1792011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Section 9.4 Air Conditioning, Heating, Cooling and Ventilation Systems Through Figure 9.5-30 Diesel Exhaust System Piping Schematic ML11178A1782011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 9.0 Auxiliary Systems, Through Figure 9.3-21 Watts Bar Nuclear Plant Boric Acid Tank Limits ML11178A1752011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Section 6.3 Emergency Core Cooling System Through 6.9 Motor-Operated Valve (MOV) Programs ML11178A1772011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 8.0 Electric Power, Through Page 8E-11 ML11178A1722011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 4.0 Reactor, Through Figure 4.4-6, Location of Incore Instrumentation System Fixed Incore Detector Core Exit Thermocouples and Iitas (Unit 2) ML11178A1732011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 5.0, Reactor Coolant System, Through Instrumentation Application 5.6-7 ML11132A1182011-05-0505 May 2011 Bellefonte, Units 1 and 2 - Proposed Regulatory Framework for the Possible Completion of Construction Activities ML1108716282011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-596, Underground Barrier Trench a, STA 5 + 78 ML1108716292011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-597, Underground Barrier Trench a, STA 7 + 78 ML1108716302011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-602 RO, Underground Barrier Trench B, STA 1 + 00 ML1108716312011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-603, Underground Barrier Trench B, STA 2 + 50 ML1108716322011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-604, Underground Barrier Trench B, STA 3 + 00 ML1108716652011-03-15015 March 2011 Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-605, Underground Barrier Trench B, STA 4 + 50 ML12257A0682011-01-0101 January 2011 Tennessee Valley Authority 2012 Watts Bar - Office of Environmental and Research Recreation Area Matrix ML11221A3222010-12-17017 December 2010 Amendment 102 to Final Safety Analysis Report (Fsar), Table 6.2.4-1, Page 1 of 69 - 64 of 69 ML1019703112010-07-16016 July 2010 Request for Additional Information Regarding Fire Protection Program ML1016005052010-06-0303 June 2010 Chapter 14 - Question 4 - Supporting Information ML1016104562010-05-27027 May 2010 Amendment 99 to Final Safety Analysis Report (Fsar), Containment Penetrations and Barriers-Table 6.2.4-1. Pages 1 Through 64 ML1013705382010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 1 of 4 ML1013705392010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 2 of 4 ML1013705372010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-281, Category 1 Conduit Banks Section F-F, Sheet 1 ML1013705342010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-71, Graphic Log & Elastic Moduli Sta. L-61+00 ML1013705312010-05-0707 May 2010 Amendment 98 to Final Safety Analysis Report, Figure 2.5-281, Category I Conduit Banks Section F-F, Sheet 2 ML1006302352010-02-25025 February 2010 Yard Holding Pond Wsel Graph Overflow for 2001 ML0935705552009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-281, Category 1 Conduit Banks, Section F-F Sheet 1 of 2 ML0935705562009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-281, Category 1 Conduit Banks, Section F-F, Sheet 1 of 2 ML0935705572009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 1 of 4 ML0935705602009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-71, Graphic Log and Elastic Moduli Sta. L-61+00 ML0935705612009-12-14014 December 2009 Final Safety Analysis Report, Amendment 96, Figure 2.5-222, Borrow Investigation 2023-03-29 Category:Report MONTHYEARWBL-24-047, Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program2024-09-25025 September 2024
[Table view]Analysis of Capsule V from the Tennessee Valley Authority Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program WBL-24-022, Cycle 5 Steam Generator Tube Inspection Report2024-05-16016 May 2024 Cycle 5 Steam Generator Tube Inspection Report WBL-24-007, Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program2024-03-0505 March 2024 Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program 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) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods 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 WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report 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 . WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-07-20020 July 2021 Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-03-23023 March 2021 Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) ML21060A9132021-03-17017 March 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Watts Bar ISFSI CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-02-25025 February 2021 Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) WBL-21-006, Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-02-11011 February 2021 Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)2020-12-16016 December 2020 Revised Pressure and Temperature Limits Report (PTLR) CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program2020-04-16016 April 2020 Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2019-10-10010 October 2019 License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019 Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019 Revised Pressure and Temperature Limits Report (PTLR) ML19039A0492019-02-0808 February 2019 Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional Redactions ML19003A5692019-01-16016 January 2019 Review of the Fall 2017 Steam Generator Tube Inspection Report ML18242A0382018-08-30030 August 2018 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)2018-08-0101 August 2018 Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information2018-04-10010 April 2018 Seismic Probabilistic Risk Assessment Supplemental Information ML17356A2692017-12-20020 December 2017 Construction Lessons Learned Report ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations2017-10-13013 October 2017 Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations ML17272A0192017-09-29029 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17263A1162017-09-20020 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17209A5542017-07-28028 July 2017 Cycle 14 Steam Generator Tube Inspection Report CNL-17-050, Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index2017-05-30030 May 2017 Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index ML16215A1042016-08-0202 August 2016 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report ML16113A0202016-04-22022 April 2016 Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information2016-03-31031 March 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program2016-02-19019 February 2016 TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit2015-09-21021 September 2015 Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report2015-07-31031 July 2015 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information CNL-15-097, Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-06-16016 June 2015 Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-039, Severe Accident Management Alternatives for Reactor Coolant Pump Seals2015-04-10010 April 2015 Severe Accident Management Alternatives for Reactor Coolant Pump Seals CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid 2024-09-25 Category:Miscellaneous MONTHYEARWBL-24-007, Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program2024-03-0505 March 2024
[Table view]Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves ML19003A5692019-01-16016 January 2019 Review of the Fall 2017 Steam Generator Tube Inspection Report ML18242A0382018-08-30030 August 2018 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report CNL-18-092, Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02)2018-08-0101 August 2018 Application to Revise the Technical Specifications to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (WBN-TS-18-02) CNL-18-007, Seismic Probabilistic Risk Assessment Supplemental Information2018-04-10010 April 2018 Seismic Probabilistic Risk Assessment Supplemental Information ML17313A1282017-11-0909 November 2017 Revised Pressure and Temperature Limits Report (PTLR) ML17272A0192017-09-29029 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17263A1162017-09-20020 September 2017 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report ML17209A5542017-07-28028 July 2017 Cycle 14 Steam Generator Tube Inspection Report ML16215A1042016-08-0202 August 2016 Technical Specification (TS) 5.9.8 - Post Accident Monitoring System Report ML16113A0202016-04-22022 April 2016 Submittal of Title 10, Code of Federal Regulations 50.59 Summary Report CNL-16-038, Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information2016-03-31031 March 2016 Application to Revise Technical Specification 4.2.1, Fuel Assemblies and Radioactive Waste System Design Basis Source Term Supplement to Response to NRC Request for Additional Information CNL-16-034, TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program2016-02-19019 February 2016 TMI Task Action I.D.1 Commitment Closure Regarding Control Room Design Review Special Program CNL-15-263, Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory2015-12-29029 December 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies (WBN-TS-15-03) - Supplemental Information Related to the Onsite Regulatory Audit at Pacific Northwest National Laboratory CNL-15-165, Submittal of Electromagnetic Interference (EMI) Survey Results2015-08-20020 August 2015 Submittal of Electromagnetic Interference (EMI) Survey Results CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 32015-07-15015 July 2015 Individual Plant Examination of External Events (IPEEE) Report, Revision 3 CNL-15-106, 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information2015-07-0808 July 2015 3, Sequoyah and Watts Bar, Units 1 & 2 - Provides Service List Update for Routine Information ML15121A6562015-05-0101 May 2015 NRC Region II - CIB1 Watts Bar 2 Ip&S 194 Additional Questions Request List CNL-15-043, Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2015-03-25025 March 2015 Flood Hazard Reevaluation Report for Watts Bar, Response to NRC Request for Information Per Title 10 of CFR 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML14163A6582014-09-18018 September 2014 Closeout of Generic Letter, 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML14212A6032014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule IR 05000391/19860602014-07-31031 July 2014 WBRD-50-391/86-60 - Final Report and Revised Completion Schedule ML14149A1502014-06-16016 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14133A5422014-05-23023 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13246A0222013-08-28028 August 2013 Submittal of Pre-op Test Instruction ML13178A2812013-06-26026 June 2013 10 CFR 50.59 Summary Report Supplement ML13144A5762013-05-22022 May 2013 Watt Bar, Units 1 & 2, Report of Drug Testing Error in Accordance with 10 CFR 26.719(c)(1) ML13126A2942013-04-29029 April 2013 10 CFR 50.59 Summary Report ML13121A0602013-04-29029 April 2013 Commitment Summary Report ML13080A3632013-03-18018 March 2013 Enclosure 3, Summer 2011 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A3662013-03-18018 March 2013 Enclosure 1, Summer 2010 Compliance Survey for Watts Bar Nuclear Plant Outfall Passive Mixing Zone ML13080A0732013-03-12012 March 2013 Extension Request Regarding the Flooding Hazard Reevaluation Report Required by NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation.. ML13175A1352013-03-0505 March 2013 2-PTI-092-03, Revision 0, Nuclear Instrumentation Source Range Noise Checks During Hot Functional Testing. ML12356A3172012-12-17017 December 2012 Submittal of Pre-op Test Instruction, 2-PTI-063-06, Revision 0, Safety Injection System Check Valve Test. ML12335A3402012-11-27027 November 2012 Tennessee Valley Authority - Fleet Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Flooding Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of ML13108A2842012-11-12012 November 2012 Unit 1, Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML13175A1362012-11-0808 November 2012 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification. ML13175A1342012-11-0101 November 2012 2-PTI-082-02, Revision 0, Rod Control - Non Hft. ML13175A1332012-10-22022 October 2012 2-PTI-085-01, Revision 0, Rod Control Functional Test. ML12236A1642012-07-19019 July 2012 Enclosure 1 Evaluation of Proposed Changes Tennessee Valley Authority Watts Bar Nuclear Plant, Unit 1 ML12223A1832012-03-29029 March 2012 Environmental Protection Agency 2012 - Facility Detail Report - Environmental Facts Warehouse Fii - Moccasin Bend Wwtp ML11362A0562011-12-20020 December 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 7 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 7 ML11341A1572011-11-30030 November 2011 Attachments 7 Through 9, WNA-CN-00157-WBT-NP, Revision 1, CAW-11-3316, and WBT-D-3566 Np, Incore Instrument System Signal Processing System Isolation Requirement ML11326A2842011-11-18018 November 2011 Commitment Summary Report ML11257A0502011-08-31031 August 2011 Attachment 7, WCAP-17427-NP, Rev. 1, Watts Bar Nuclear Plant Unit 2 Common Q Post Accident Monitoring System Computer Security Assessment, Attachment 8, Application for Withholding Proprietary Information from Public Disclosure and Attachme ML1104003852011-02-0707 February 2011 Enclosure 2, Appendix a, Hydrothermal Effects on the Ichthyhoplankton from the Watts Bar Nuclear Plant Supplemental Condenser Cooling Water Outfall in Upper Chickamauga Reservoir 2024-03-05 |
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