Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ML20133K7725 August 1985Forwards Response to NUREG-0737,TMI Item II.F.2 & SER Confirmatory Item 15 Re Inadequate Core Cooling Monitoring Sys.Subset of Monitoring Sys That Provides Rev 2 to Reg Guide 1.97 post-accident Instrumentation Consolidated
ML20140E9385 March 1986Forwards Response to NUREG-0737,TMI Item II.F.2 & SER Confirmatory Item 15 Re Inadequate Core Cooling Monitoring Sys.Core Exit Thermocouples in Reactor Vessel Water Level Sys Replaced W/Rcs Hot Leg wide-range RTDs
ML20149D62831 January 1988Safety Evaluation Report Related to the Operation of Vogtle Electric Generating Plant,Units 1 and 2.Docket Nos. 50-424 and 50-425.(Georgia Power Co,Et Al)
ML20203K85023 April 1985Rev 0 to Training Lesson Plan LO-LP-36102-00-C, Recognizing Core Damage:In-Core Instruments
ML20207C70022 December 1986Discusses Plant Safety Monitoring Sys.Sys Processes & Outputs Reg Guide 1.97,Rev 2 Variables to Internal Plasma Displays & External Indicators,Displays,Cabinets & Other Equipment.Sys Testing Described
ML20210L9565 February 1987Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1
ML20214S5861 June 1987Forwards Verification & Validation:Final Rept for Plant Safety Monitoring Sys. All Trouble Repts Resolved.Only One Validation Trouble Rept Re Human Engineering Deficiencies Remains Open
ML20214S62830 June 1987Verification & Validation:Final Rept for Plant Safety Monitoring Sys
ML20215M87427 October 1986Emergency Operating Procedures,Reactor Operator Simulator Training
ML20235L7697 July 1987Forwards J Frawley Rept Re Audit of Plant Safety Monitoring Sys Conducted at Westinghouse on 870629-30.Concurrence W/ Findings of Rept Given
ML20235X36120 July 1987Summary of 870629-30 Meetings W/Util in Monroeville,Pa Re Audit of Plant Safety Monitoring Sys Verification & Validation Program.List of Attendees & Viewgraphs Encl
ML20247A89716 March 1989Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl
ML20311A3446 November 20172017 Q1-Q4 ROP Inspection Findings
ML21102A22430 March 20213 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls (Part 2) & Chapter 8, Electric Power (Part 1)
ML21102A22830 March 20213 to Updated Final Safety Analysis Report, Chapter 4, Reactor (Part 2); Chapter 5, Reactor Coolant System and Connected Systems; & Chapter 6, Engineered Safety Features (Part 1)
ML21102A23430 March 20213 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features (Part 3) & Chapter 7, Instrumentation and Controls (Part 1)
ML21179A11015 June 20210 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of the Plant
ML22179A14815 June 2022Technical Specifications Bases, Revision 70
ML22220A20010 August 2022Attachment 2 - NUREG-2194, Vol. 2, Rev. 1, Standard Technical Specifications, Westinghouse Advanced Passive 1000 Plants. Volume 2, Bases
ML22326A11631 October 20224 to the Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features (Part 3 of 3) and Chapter 7, Instrumentation and Controls (Part 1 of 2)
ML23165A21513 June 2023Enclosure 1: Vogtle Electric Generating Plant, Units 3 and 4, Updated Final Safety Analysis Report, Revision 12
ML23165A21913 June 2023Enclosure 9: Vogtle Electric Generating Plant, Units 3 and 4, Technical Specifications Bases, Revision 73
ND-19-1095, (VEGP) Units 3 and 4 - Emergency Action Levels and Basis18 April 2019(VEGP) Units 3 and 4 - Emergency Action Levels and Basis
NL-03-1140, Changes to Technical Specification Bases11 June 2003Changes to Technical Specification Bases
NL-03-1365, Revision to Bases24 June 2003Revision to Bases
NL-04-0564, Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors21 May 2004Joseph M. Farley Nuclear Plant, and Vogtle Electric Generating Plant, Application for Technical Specification Amendment to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors
NL-04-2205, Changes to Technical Specification Bases10 November 2004Changes to Technical Specification Bases
NL-07-0084, License Amendment Request to Revise Technical Specifications, Southern Nuclear Operating Company Reorganization30 January 2007License Amendment Request to Revise Technical Specifications, Southern Nuclear Operating Company Reorganization
NL-09-2040, Third 10-Year Interval ISI Plan15 January 2010Third 10-Year Interval ISI Plan
NL-10-0794, License Amendment Request for Incorporation of Previously NRC Approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-5-A, Rev. 116 December 2010License Amendment Request for Incorporation of Previously NRC Approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-5-A, Rev. 1
NL-15-0820, Vogtle, Units 1 and 2 - Emergency Plan, Revision 6431 March 2015Vogtle, Units 1 and 2 - Emergency Plan, Revision 64
NL-15-1569, Revision 65 to Emergency Plan17 August 2015Revision 65 to Emergency Plan
NL-15-1898, Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 3 of 43 March 2016Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 3 of 4
NL-15-1898, Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 83 March 2016Enclosure 5: Marked-Up EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant. Part 2 of 8
NL-15-1898, Enclosure 6: Clean-Typed EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant3 March 2016Enclosure 6: Clean-Typed EAL Schemes - License Amendment Request for Changes to EAL Schemes to Adopt NEI 99-01 Rev. 6 and to Modify Radiation Monitors at Farley Nuclear Plant
NL-16-1409, Submittal of Report of Changes to Emergency Plan22 August 2016Submittal of Report of Changes to Emergency Plan
NL-16-1830, Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1C of 1C3 November 2016Southern Nuclear Operating Company Response to RAI for License Amendment Regarding Emergency Action Level Schemes to Adopt NEI 99-01 Rev 6 and to Modify Radiation Monitors at Farley Nuclear Plant, Part 1C of 1C
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications2 November 2016Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.22 November 2016Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)2 November 2016Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)
NL-18-0915, Enclosures 1, 3, 4 & 5 - Introduction and Overall Summary, Risk Quantification, Defense-in-Depth & Safety Margin and Supplemental Response to NRC Generic Letter 2004-0210 July 2018Enclosures 1, 3, 4 & 5 - Introduction and Overall Summary, Risk Quantification, Defense-in-Depth & Safety Margin and Supplemental Response to NRC Generic Letter 2004-02
NL-21-0265, 3 to Updated Final Safety Analysis Report, Bases for Improved Technical Specifications30 March 20213 to Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
NL-22-0208, License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-49030 June 2022License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490
NRC Generic Letter 1985-0217 April 1985NRC 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 1985-0531 January 1985NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
NRC Generic Letter 1985-0823 May 1985NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format
NRC Generic Letter 1985-0923 May 1985NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3
NRC Generic Letter 1992-0419 August 1992NRC 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 1998-0228 May 1998NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
Retrieved from "https://kanterella.com/Special:Ask"