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Issue date | Title | |
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RA-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change | 24 April 2023 | Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change |
RA-23-0091, Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 4 | 13 April 2023 | Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 4 |
RA-22-0218, Emergency Action Level (EAL) Technical Basis Document, Revision 3 | 14 July 2022 | Emergency Action Level (EAL) Technical Basis Document, Revision 3 |
RA-20-0009, Emergency Plan, Revision 20-01 | 15 January 2020 | Emergency Plan, Revision 20-01 |
CNS-17-013, Emergency Plan, Revision 17-1 | 19 April 2017 | Emergency Plan, Revision 17-1 |
ML16055A230 | 19 February 2016 | Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Redline Version. Part 3 of 4 |
CNS-16-010, Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Clean Version. Part 4 of 4 | 19 February 2016 | Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Clean Version. Part 4 of 4 |
CNS-16-015, Technical Specification Bases Changes | 18 February 2016 | Technical Specification Bases Changes |
CNS-15-098, Technical Specification Bases Changes | 14 December 2015 | Technical Specification Bases Changes |
ML15125A135 | 30 April 2015 | License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors, Dated November 2012 |
ML14240A666 | 27 October 2014 | 301 Draft SRO Written Examination |
CNS-14-055, Technical Specification Bases Changes | 5 May 2014 | Technical Specification Bases Changes |
ML13336A396 | 26 November 2013 | 301 Draft RO Written Examination |
ML12290A022 | 11 October 2012 | Technical Specification Bases Changes |
ML14357A323 | 19 May 2011 | Revision 11-1, Update to Emergency Plan |
ML111540489 | 2 February 2011 | Initial Exam 2010-301 Draft RO Written Exam |
ML080670419 | 7 March 2008 | CDBI Findings |
ML050630430 | 1 March 2005 | Tech Spec Pages for Amendments 219 & 214 Elimination of Requirements for Hydrogen Recombiners and Monitors |
ML041600607 | 27 May 2004 | License Amendment Request to Eliminate Requirements for Hydrogen Recombiners (Technical Specification 3.6.7) & Requirements for Hydrogen Monitors (Technical Specification 3.3.3), Using the CLIIP |
ML20210N315 | 4 August 1999 | Proposed Tech Specs Changing TSs 3.3.2, ESFAS Instrumentation, 3.3.3, Post Accident Monitoring Instrumentation, 3.4.14, RCS Loops - Test & 5.3, Unit Staff Qualifications |
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
ML20151T949 | 8 September 1998 | Proposed Tech Specs & Bases Re Relocation from Current TS & Scheduling of New More Restrictive Surveillance Requirements |
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 |
ML20199A642 | 22 January 1998 | Safety Evaluation Accepting Proposed EALs Changes for Plant, Units 1 & 2.Concludes That Changes Consistent W/Guidance in NUMARC/NESP-007,w/variations as Identified & Accepted in Review & Meets Requirements of 10CFR50.47(b)(4) |
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
ML20212C265 | 21 October 1997 | Forwards Addl Info Requested Re EAL Rev to NUMARC/NESP-007 Methodology |
ML20137N837 | 29 March 1997 | Forwards Response to Issues Re Classification Scheme of Emergency Action Levels |
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
ML20117L568 | 29 August 1996 | Forwards Classification Scheme Provided in NUMARC/NESP-007, Rev 2 for Site for Review & Approval |
ML20117L503 | 29 August 1996 | Forwards Classification Scheme Provided in NUMARC/NESP-007, Rev 2,for Site,Table Showing Disposition of NUMARC/NESP-007, Rev 2,classification Procedure & Concurrence Ltrs |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
ML20112G996 | 6 June 1996 | Proposed Tech Specs,Reflecting Separate Volumes |
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
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) |
ML20094P561 | 1 April 1992 | Submits 1991 10CFR50.59 Summary of Nuclear Station Mods, Exempt Change Variation Notices,Changes to Selected License Commitment Manual,Procedure Changes,Tests & Experiments from Oct 1990 to Sept 1991 |
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
ML20248G940 | 2 October 1989 | Response to NRC Re Violation Noted in Insp Rept 50-414/89-19.Corrective Actions:Station Problem Rept Initiated to Examine Feasibility of Using Alternate Means of Venting Reactor Vessel Head |
ML20247C702 | 31 August 1989 | Notice of Violation from Insp on 890616-28.Violation Noted: from 890602-16,both Channels of Reactor Vessel Water Level Instrumentation Inoperable in Modes 1,2 & 3 Due to Closure of Isolation Valves on upper-range Pressure Transmitters |
IR 05000413/1989019 | 13 July 1989 | Insp Repts 50-413/89-19 & 50-414/89-19 on 890616-0628. Violations Noted.Major Areas inspected:890616 Event Re Channels of Reactor Vessel Level Instrumentation Sys Inoperable for Period of Time in Excess of Tech Specs |
ML20151Q166 | 28 July 1988 | Forwards Plan Providing Hydrogen & Steam Release Histories to Containment for Spectrum of Accident Sequences Using MAAP for Mechanistic Portion of Calculation |
ML20153E959 | 4 May 1988 | Proposed Tech Spec 3.3.3.6 & Tables 3.3-10 & 4.3-7 Reflecting Reg Guide 1.97 Reviews |
ML20148H285 | 22 January 1988 | Summary of ACRS Subcommittee on Generic Items 871216 Meeting W/Util in Washington,Dc Re Effectiveness of NRC Process That Deals W/Generic Issues & Usis.Viewgraphs & Presentation Schedule Encl |