Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ELV-03500, Provides Plant Attribute Library (Pal) & Data Point Library (Dpl) as Requested in Rev 1 to NUREG-139417 March 1992Provides Plant Attribute Library (Pal) & Data Point Library (Dpl) as Requested in Rev 1 to NUREG-1394
ELV-03978, Forwards Mods to Current Data Point Library Listing,Per J Jolicoeur Request.Util Currently Scheduled to Perform Factory Acceptance Testing W/Nrc Integration Contractor on 92090131 August 1992Forwards Mods to Current Data Point Library Listing,Per J Jolicoeur Request.Util Currently Scheduled to Perform Factory Acceptance Testing W/Nrc Integration Contractor on 920901
IR 05000424/19860739 September 1986Insp Rept 50-424/86-73 on 860818-22.No Violations or Deviations Noted.Major Areas Inspected:Proposed Startup Tests
IR 05000424/198609917 November 1986Insp Rept 50-424/86-99 on 861014-17.No Violations or Deviations Noted.Major Areas Inspected:Review of Startup Testing Procedures
IR 05000424/199330013 September 1993Exam Rept 50-424/93-300 on 930816-20.No Violations or Deviations Noted.One Inspector follow-up Item Re Failure to Provide Operators W/Tools to Accomplish Emergency Procedure 19100-C,Step 14 Noted.Exam Results:Four SROs Passed
IR 05000424/200300427 October 2003IR 05000424-03-004 & 05000425-03-004, on 06/29/03 Through 09/27/03, for Vogtle Electric Generating Plant, Waynesboro, Ga; Licensed Operator Requalification, Maintenance Risk Assessments & Emergent Work Evaluation & Refueling & Outage Activi
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown11 December 1996Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent Events Involving Reactor Coolant System Inventory Control During Shutdown
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML04055051820 February 2004Technical Specification Amendment 96 & 74 to Vogtle Units 1 &2
ML0506804507 March 2005Technical Specifications, Elimination of Hydrogen Recombiners and Monitors Requirements
ML0806704197 March 2008CDBI Findings
ML0909204373 June 2009Issuance of Renewed Facility Operating License No NPF-68 and NPF-81 for the Vogtle Electronic Generating Plant, Units 1 and 2
ML09328035318 November 2009Initial Exam 2009-301 Final SRO Written Exam
ML11096A06413 June 2011Issuance of Amendments 264, 208, 161 & 143, Regarding Technical Specification Change
ML1122702298 August 2011301 Draft SRO Written Exam
ML14311A6133 January 2005Submittal of Emergency Plan, Revision 61
ML14338A0593 December 2014301 Draft SRO Written Exam
ML15138A22731 March 2015Emergency Plan, Revision 64
ML16071A1363 March 2016Enclosure 2: EAL Deviations and Differences Maxtrix (Farley, Hatch, and Vogtle) Part 3 of 4
ML16071A1803 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
ML16071A1953 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
ML16130A57731 May 2016Issuance of Amendments Technical Specification End States
ML16330A3982 November 2016Updated Final Safety Analysis Report, Table 4.3-1 (Sheet 1 of 3) Through Figure 6-2.1-15 (Sheet 14 of 65)
ML16330A4162 November 2016Updated Final Safety Analysis Report, Bases for Improved Technical Specifications
ML17032A1392 November 2016Updated Final Safety Analysis Report, Section 15.2
ML18057B46426 February 201805000424/2017301 and 05000425/2017301 Exam Final Items 2B - Delay Release 2 Yrs
ML19115A28725 April 2019301 ADAMS-2B Exam Final Items
ML20012E97627 March 1990Requests Withdrawal of Inservice Insp Relief Requests RR-45, RR-47,RR-48 & Conditional Withdrawal of RR-54 Based on Reasons Discussed in Encl,Per 900206 Conference Call
ML20020A00931 January 2020WCAP-18461-NP, Rev. 0, Common Q Platform and Component Interface Module System Elimination of Technical Specification Surveillance Requirements
ML20059J0063 November 1993Safety Evaluation Supporting Rev 15 to Emergency Plan for Plant
ML20071M15521 July 1994Util Answer to Intervenor Motion to Accept Addl Factual Bases in Support of Admitted Contention.* Concludes That Intervenor Motion Should Be Denied.W/Certificate of Svc & Svc List
ML20076H00017 October 1994Forwards Revised Emergency Response Data Sys -- Unit 1 Data Point Library Point Listing for Vogtle Electric Generating Plant
ML20080P08222 July 1994Transcript of a Mosbaugh 940722 Deposition in Atlanta,Ga. Pp 1-208.Supporting Info Encl
ML20100G03719 February 1996Proposed Tech Specs Based on NUREG-1431
ML20107E38230 January 1985Conformance to Reg Guide 1.97,Vogtle Electric Generating Plant,Units 1 & 2
ML20112C43015 March 1985Forwards Response to NRC Request for Addl Info Re Draft SER Item 62,Reg Guide 1.97,Rev 2 & Proposed FSAR Changes. Includes Info Re Reactor Vessel Water Level,Containment Isolation Valve Status & Pressurizer Heater Status
ML20127L61820 June 1985Responds to 850515 Request for Addl Info Re Draft SER Open Item 62 Concerning Plant Conformance to Rev 2 to Reg Guide 1.97.Containment Isolation Valve Status Conforms to Reg Guide Category I Instrumentation Criteria
Retrieved from "https://kanterella.com/Special:Ask"