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| Issue date | Title | |
|---|---|---|
| ML19318A847 | 9 June 1980 | Responds to IE Bulletin 80-12 Re Decay Heat Removal Sys Reliability.Forwards Results of Investigation.Administrative Procedural Changes Instituted to Require at Least Two Independent Means of Supplying Adequate Heat Removal |
| ML19326E112 | 3 July 1980 | TVA Response to NUREG-0578,Short-Term Lessons Learned Requirements. |
| ML19338C750 | 2 September 1980 | Core Degradation Program,Vol 1:Hydrogen Study. |
| ML20041G419 | 15 March 1982 | Forwards Final post-accident Monitoring Instrumentation List & Design Criteria for Compliance W/Reg Guide 1.97 |
| ML20062L636 | 12 August 1982 | Application to Amend License DPR-77,changing License Conditions Re Low Temp Overpressure Protection,Addl Accident Monitoring Instrumentation,Rcs vents,post-accident Sampling, Instruments for Inadequate Core Cooling & Emergency Support |
| ML20069B539 | 20 May 1994 | Responds to NRC Re Violations Noted in Insp Repts 50-327/94-04 & 50-328/94-04.Corrective Actions:Vct Temp Raised,Reactor Head Vented & Appropriated Plant Procedure Revised to Address Operation RCS at Atmospheric Pressure |
| ML20072D482 | 16 June 1983 | Application for Amend to License DPR-79,proposing Changes to License Conditions Re post-accident Sampling.Description of Proposed Changes,Justification & Significant Hazards Determination for Proposed License Conditions Encl |
| ML20082E466 | 6 April 1995 | Proposed Tech Specs,Deleting License Condition 2.c |
| ML20084R130 | 2 June 1995 | Forwards Response to NRC 950315 RAI Re Emergency Action Plan Conversion to NUMARC Eals.Revised EALs Which Occurred as Result of 950322 Meeting Between NRC & TVA & Rev 16 to EPIP-1, Emergency Plan Classification Matrix Also Encl |
| ML20095C690 | 31 July 1984 | Draft Sequoyah Nuclear Plant Integrated Containment Analysis, Technical Rept |
| ML20095C773 | 7 August 1984 | Draft, Peach Bottom Atomic Power Station Integrated Containment Analysis, Technical Rept |
| ML20099B210 | 24 July 1992 | Forwards Updated Emergency Response Data Sys Data Point Library,Per NRC Request |
| ML20101G813 | 22 June 1992 | Forwards Addl Info Requested to Update Data Point Library for Snp Units 1 & 2 |
| ML20108D133 | 31 December 1984 | Preliminary Sequoyah Nuclear Plant,Integrated Containment Analysis,Idcor Task 23.1,Final Rept |
| ML20141H701 | 19 May 1997 | Provides ERDS Data Point Library Update for Unit 1.Encl Contains Revised Listing |
| ML20154J429 | 31 May 1988 | Safety Evaluation Report on Tennessee Valley Authority. Sequoyah Nuclear Performance Plan |
| ML20205L265 | 31 May 1985 | Technical Rept 23.1S Sequoyah Nuclear Plant Integrated Containment Analysis. W/870313 Release Ltr |
| ML20212B760 | 21 October 1997 | Requests for Technical Review of Encl Draft in 97-076 Re Inadvertent Draindown at Plant,Unit 1 |
| ML20247F346 | 13 March 1989 | Special Team Insp Repts 50-327/89-05 & 50-328/89-05 on 890131-0209.Violations Noted.Major Areas Inspected:Radwaste, Radiological Controls,Corporate QA Audits & Site Chemistry |
| ML21245A267 | 27 October 2021 | NON-PROPRIETARY - Sequoyah Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 356 and 349 Regarding the Transition to Westinghouse Robust Fuel Assembly-2 (RFA-2) Fuel |
| 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 | 19 June 2015 | 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 |
| NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9 | 24 July 2015 | Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 2 of 9 |
| 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 |