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Issue date | Title | |
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ML12235B359 | 13 August 2012 | OL - 2012-08-13 - WBN Project Plan - Unit 2.pdf |
ML12235B360 | 16 August 2012 | OL - 2012-08-16 - WBN Project Plan - Unit 2.pdf |
ML12235B361 | 20 August 2012 | OL - 2012-08-20 - WBN Project Plan - Unit 2.pdf |
ML12235B362 | 16 August 2012 | OL - TVA Letter to NRC_2012-08-15 - Regulatory Framework Submittal Letter Rev 8 |
ML12242A476 | 27 August 2012 | Update to Technical Specification (TS) Table 3.3.3-1 and Technical Specification Bases (Tsbs) 3.3.3 |
ML12244A070 | 23 August 2012 | Final Safety Analysis Report (Fsar), Amendment 109 - Section 5, Reactor Coolant System - Page 5-I Through 5.6-8 |
ML12261A172 | 27 August 2012 | OL - 2012-08-27 - WBN Project Plan - Unit 2.pdf |
ML12261A173 | 27 August 2012 | OL - TVA Letter to NRC_08-27-2012__TS Table 3.3.3-1 and Tsb 3.3.3 |
ML13023A315 | 17 January 2013 | Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 9 (TAC No. MD6311), and Status of Generic Communications for Unit 2 -Revision 9 |
ML13036A245 | 17 January 2013 | OL - TVA Letter to Nrc_Regulatory Framework Submittal Letter Rev 9 |
ML13210A063 | 26 July 2013 | Initial Exam 2013-301 Final Administrative JPMs |
ML13213A194 | 25 July 2013 | Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 10 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 10 |
ML13255A279 | 14 August 2013 | Final Safety Analysis Report (Fsar), Amendment 110, Section 5, Reactor Coolant System |
ML13357A050 | 12 December 2013 | Synopsis of Revisions Included in Watts Bar Unit 2 Developmental Revision H of Technical Specifications and Technical Specification Bases. Part 1 of 2 |
ML13357A053 | 12 December 2013 | Technical Specifications |
ML14055A276 | 18 February 2014 | Pre-Operational Test Instruction 2-PTI-063-01, Safety Injection System SIS Integrated Test. |
ML14080A023 | 11 March 2014 | Submittal of Pre-Operational Test Instruction |
ML14160B105 | 30 May 2014 | Final Safety Analysis Report, Amendment 112, Section 5.0, Reactor Coolant System |
ML14170A045 | 16 June 2014 | Attachment 1 - TS Developmental Revision I Changes (Mark-Up) for WBN Unit 2 |
ML14357A319 | 26 April 2004 | TVA Nuclear Radiological Emergency Plan (Rep), Revision 73 |
ML15251A587 | 22 October 2015 | Issuance of Facility Operating License No. NPF-96 Watts Bar Nuclear Plant, Unit 2 |
ML15279A272 | 11 September 2015 | Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System |
ML15301A140 | 22 October 2015 | Current Facility Operating License NPF-96, Tech Specs, Revised 11/08/2017 |
ML16257A721 | 13 September 2016 | Initial Exam 2016-301 Final SRO Written Exam - Delay Release 2 Years |
ML17165A483 | 14 June 2017 | 302 Draft Simulator Scenarios |
ML17165A493 | 14 June 2017 | 302 Final Simulator Scenarios |
ML17180A024 | 11 July 2017 | Issuance of Amendment Regarding One-Time Extension of Intervals for Specified Surveillance Requirements |
ML17334A170 | 2 November 2017 | Amendment 1 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System |
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System | 11 September 2015 | Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System |
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 | 17 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. |
NRC Generic Letter 1985-02 | 17 April 1985 | NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
WBL-22-026, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual | 11 May 2022 | Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual |
WBL-23-045, 10 CFR 50.59 Summary Report | 7 November 2023 | 10 CFR 50.59 Summary Report |