NL-14-119, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - July 2014 Status Report: Difference between revisions
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| contact person = | | contact person = | ||
| case reference number = CNL-14-119, L44 140731 001 | | case reference number = CNL-14-119, L44 140731 001 | ||
| document type = Letter | | document type = Letter type:NL | ||
| page count = 15 | | page count = 15 | ||
}} | }} | ||
Revision as of 08:58, 11 October 2018
| ML14212A748 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 07/31/2014 |
| From: | Shea J W Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNL-14-119, L44 140731 001 | |
| Download: ML14212A748 (15) | |
Category:Letter type:NL
MONTHYEARNL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020
[Table view]30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material NL-18-067, Watts Bar Nuclear Plant, Units 1 & 2 - Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)2018-10-12012 October 2018 Watts Bar Nuclear Plant, Units 1 & 2 - Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) NL-18-004, Browns Station - American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section Xi, Inservice Inspection (ISI) Program, Unit 1 Third Ten-Year Inspection Interval, Unit 2 Fifth Ten-Year Inspection Interval, and Unit 3 Four2018-05-11011 May 2018 Browns Station - American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section Xi, Inservice Inspection (ISI) Program, Unit 1 Third Ten-Year Inspection Interval, Unit 2 Fifth Ten-Year Inspection Interval, and Unit 3 Fourt NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec NL-18-038, Browns Ferry, Units 1, 2, and 3, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-2018-03-0909 March 2018 Browns Ferry, Units 1, 2, and 3, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-0 NL-18-016, Watts Bar, Unit 2 - Application to Revise License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)2018-03-0505 March 2018 Watts Bar, Unit 2 - Application to Revise License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) NL-17-119, Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2018-02-28028 February 2018 Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) NL-18-021, Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) .2018-02-0808 February 2018 Supplement to Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plants, Units 1 and 2 License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 2.4, Qptr, and TS 3.3.1, 'Reactor Trip System (RTS) .. NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. NL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23)2017-10-11011 October 2017 Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)2017-08-0707 August 2017 Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014) NL-17-067, Browns Ferry, Units 1, 2, and 3 - Administrative Changes to Proposed Revised Technical Specification Pages Related to Application to Revise Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request an A2017-06-29029 June 2017 Browns Ferry, Units 1, 2, and 3 - Administrative Changes to Proposed Revised Technical Specification Pages Related to Application to Revise Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request an Al NL-17-027, Watts Bar, Unit 2, Application to Modify Operating License Condition Regarding the Actions to Resolve Issues Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System (391-WBN-TS-17-06)2017-03-28028 March 2017 Watts Bar, Unit 2, Application to Modify Operating License Condition Regarding the Actions to Resolve Issues Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System (391-WBN-TS-17-06) NL-17-026, Watts Bar, Unit 1 - Application to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (390-WBN-TS-17-04)2017-03-16016 March 2017 Watts Bar, Unit 1 - Application to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (390-WBN-TS-17-04) NL-17-012, Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A2017-01-17017 January 2017 Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A NL-16-193, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Spent Fuel Pool Evaluation Supplement2016-12-21021 December 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, Spent Fuel Pool Evaluation Supplementa NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat2016-10-31031 October 2016 Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificati NL-16-141, Watts Bar, Units 1 & 2, Application to Modify Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System.2016-10-20020 October 2016 Watts Bar, Units 1 & 2, Application to Modify Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System. 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) NL-16-114, Browns Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Powe2016-08-0303 August 2016 Browns Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Containment Accident Pressure Credit Elimination Updates on Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power NL-16-031, Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications Regarding Discrepancies in Control Room Ventilation and Other Administrative Changes to the Technical Specifications (WBN-TS-16-03)2016-06-0707 June 2016 Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications Regarding Discrepancies in Control Room Ventilation and Other Administrative Changes to the Technical Specifications (WBN-TS-16-03) NL-16-033, Watts Bar, Unit 2 - Application to Modify Technical Specifications Regarding Steam Generator Minimum Narrow Range Level Error Correction2016-05-16016 May 2016 Watts Bar, Unit 2 - Application to Modify Technical Specifications Regarding Steam Generator Minimum Narrow Range Level Error Correction NL-15-210, Sequoyah Nuclear Plant, Units 1 and 2 - Withdrawal of Proposed Technical Specification Change, Ultimate Heat Sink (UHS) Temperature Limitations Supporting Alternate Essential Raw Cooling Water (ERCW) Loop Alignments (SQN-TS-13-01 and 13-022015-10-22022 October 2015 Sequoyah Nuclear Plant, Units 1 and 2 - Withdrawal of Proposed Technical Specification Change, Ultimate Heat Sink (UHS) Temperature Limitations Supporting Alternate Essential Raw Cooling Water (ERCW) Loop Alignments (SQN-TS-13-01 and 13-02) 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 NL-15-181, Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mod2015-09-0303 September 2015 Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode NL-15-158, Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor.2015-08-0303 August 2015 Supplement to TVA Letter, Sequoyah Nuclear Plant - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor. NL-15-151, Watts Bar Nuclear Plant Unit 2 - Diesel Generator Frequency - Response to NUREG 0847 Supplemental Safety Evaluation Report (Sser) 22, Open Item 32 - Correction2015-07-24024 July 2015 Watts Bar Nuclear Plant Unit 2 - Diesel Generator Frequency - Response to NUREG 0847 Supplemental Safety Evaluation Report (Sser) 22, Open Item 32 - Correction NL-15-098, Sequoyah, Units 1 and 2 - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor2015-07-10010 July 2015 Sequoyah, Units 1 and 2 - Revision to Commitment No. 28 and Review of Impacts to the SQN Reactor Vessel Internals Aging Management Program Due to Dislodged Reactor Vessel Surveillance Capsules in Unit 1 Reactor NL-15-125, Browns Ferry, Unit 1 - American Society of Mechanical Engineers (ASME) Section Xi, Lnservice Inspection (Lsi) and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-272015-06-26026 June 2015 Browns Ferry, Unit 1 - American Society of Mechanical Engineers (ASME) Section Xi, Lnservice Inspection (Lsi) and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-27 NL-15-020, Sequoyah, Units 1 and 2 - Supplement to the Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) and Response to NRC Requests for Additional In2015-04-10010 April 2015 Sequoyah, Units 1 and 2 - Supplement to the Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) and Response to NRC Requests for Additional Inf NL-14-100, Browns Ferry, Units 1, 2 & 3 - Tennessee Valley Authority'S Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Sever2014-06-30030 June 2014 Browns Ferry, Units 1, 2 & 3 - Tennessee Valley Authority'S Phase 1 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe NL-14-081, Browns Ferry, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Fer2014-05-16016 May 2014 Browns Ferry, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferr NL-14-009, Sequoyah, Units 1 & 2 and Watts Bar, Unit 1, Response to NRC Request for Additional Information Related to Review of Potential Breaches of Hesco Modular Flood Barriers and Earthen Embankments Affecting the Updated Hydrologic Analysis Resul2014-01-31031 January 2014 Sequoyah, Units 1 & 2 and Watts Bar, Unit 1, Response to NRC Request for Additional Information Related to Review of Potential Breaches of Hesco Modular Flood Barriers and Earthen Embankments Affecting the Updated Hydrologic Analysis Result NL-14-007, Follow-up Response to NRC Request for Additional Information Related to Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number E2014-01-10010 January 2014 Follow-up Response to NRC Request for Additional Information Related to Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA 2020-07-22 |