Pages that link to "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 Pre"
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The following pages link to 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 Pre:
Displayed 50 items.
- ML15348A056 (← links)
- ML15282A223 (← links)
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- ML15176A682 (← links)
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- ML18025A323 (← links)
- ML18155A487 (← links)
- 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 Four (← links)
- 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- (← links)
- NL-18-016, Watts Bar, Unit 2 - Application to Revise License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) (← links)
- 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) (← links)
- 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) . (← links)
- 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 System (← links)
- 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) (← links)
- 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) (← links)
- 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 A (← links)
- 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) (← links)
- 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) (← links)
- NL-17-015, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Transmittal of Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 36, Transmission System Update -Saf (← links)
- 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-A (← links)
- 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 Supplement (← links)
- 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 Specificat (← links)
- 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 Powe (← links)
- 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) (← links)
- NL-16-033, Watts Bar, Unit 2 - Application to Modify Technical Specifications Regarding Steam Generator Minimum Narrow Range Level Error Correction (← links)
- 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 13-02 (← links)
- NL-15-169, ANP-2860NP Revision 2, Supplement 2, Browns Ferry Unit 1 - Summary of Responses to Request for Additional Information, Extension for Use of Atrium 10XM Fuel for Extended Power Uprate. (← links)
- 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 Ma (← links)
- 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 - Mod (← links)
- 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-27 (← links)
- NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8 (← links)
- NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 5 of 8 (← links)
- NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 4 of 8 (← links)
- NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 3 of 8 (← links)
- NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8 (← links)
- NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 1 of 8 (← links)
- 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 In (← links)
- 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 Sever (← links)
- 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 Fer (← links)
- 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 Resul (← links)
- 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 E (← links)
- 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. (← links)
- 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) (← links)
- 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 - Correction (← links)
- 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) (← links)
- 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. (← links)