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Issue date | Title | |
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IR 05000266/1993015 | 22 December 1993 | Insp Repts 50-266/93-15 & 50-301/93-15 on 931026-1206. Violations Noted.Major Areas Inspected:Plant Operations, Maint,Engineering,Plant Support & Corrective Actions on Previous Findings |
IR 05000266/2020001 | 13 May 2020 | Integrated Inspection Report 05000266/2020001 and 05000301/2020001 |
IR 05000266/2022004 | 24 January 2023 | Integrated Inspection Report 05000266/2022004 and 05000301/2022004 |
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 |
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 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
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 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
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 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 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 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 |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
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 |
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 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 |
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 |
L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 | 29 July 2022 | Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02 |
L-95-020, Forwards Public Ver of Revised Epips,Including Rev 32 to EPIP Index,Rev 12 to EPIP 2.1,rev 23 to EPIP 4.1,rev 15 to EPIP 7.3.1 & Rev 13 to EPIP 10.2 | 31 August 1995 | Forwards Public Ver of Revised Epips,Including Rev 32 to EPIP Index,Rev 12 to EPIP 2.1,rev 23 to EPIP 4.1,rev 15 to EPIP 7.3.1 & Rev 13 to EPIP 10.2 |
ML020730408 | 2 February 2002 | Initial SRO Examination 02/2002 |
ML022280354 | 8 August 2002 | DAEC Emergency Planning Department Procedure Transmittal Acknowledgment Memo |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML040420424 | 30 January 2004 | Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process |
ML042310523 | 13 August 2004 | Technical Specifications, Relocation of Requirements for Hydrogen Monitors |
ML051050045 | 9 April 2004 | RCE 254, Potential Loss of Hot Leg Vent Path During Nozzle Dam Installation. |
ML051400268 | 8 October 2004 | Enclosures V & VI Point Beach Revised EAL Submittal, Justification Matrix Reference Material |
ML053480122 | 22 December 2005 | Appendix a - Technical Specifications |
ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
ML080670419 | 7 March 2008 | CDBI Findings |
ML14342A150 | 9 December 2009 | Nextera Energy Point Beach, LLC Point Beach Nuclear Plant, Units 1 and 2, Revision 53 of Emergency Plan |
ML16251A156 | 1 September 2016 | Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control |
ML17363A145 | 21 December 2017 | Response to Request for Additional Information Regarding License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactor |
ML19257A292 | 31 December 1979 | Forwards Supplementary Response to short-term TMI Lessons Learned Task Force Requirements & Provides Schedule of Implementation of Commitments.Seven Oversize Drawings Encl |
ML20010G951 | 14 September 1981 | Forwards Response to NUREG-0737, Clarification of TMI Action Plan Requirements. Addl Info Provided Re Current Schedule & Implementation Status |
ML20052C887 | 26 April 1982 | Forwards Update to NUREG-0737 Schedule Requirements & Implementation Status |
ML20054H281 | 14 June 1982 | Forwards Request for Addl Info Re Proposed Reactor Vessel Water Level Indication Sys.Info Should Be Submitted within 30 Days of Receipt of Ltr |
ML20058G886 | 28 July 1982 | Forwards Response to NRC 820619 Request for Addl Info Re Proposed Reactor Vessel Water Level Instrumentation Sys Required by NUREG-0737,Item II.F.2 |
ML20065H145 | 29 September 1982 | Advises That Error Analysis of Reactor Vessel Water Level Instrumentation Sys Requested in NRC Will Be Available by 830115 |
ML20067E048 | 31 January 1991 | Responds to NRC Re Violations Noted in Insp Repts 50-266/90-22 & 50-301/90-22.Corrective Actions:Proposed Procedure Pbnp 2.1.3, Temporary Changes to Procedures Drafted & Will Be Issued by 910401 |
ML20069G572 | 21 March 1983 | Forwards Response to Generic Ltr 82-28, Inadequate Core Cooling Instrumentation Sys, Including Response to NUREG-0737,Item II.F.2 |
ML20070Q853 | 19 January 1983 | Forwards Instrumentation Error Analysis of Reactor Vessel Water Level Indication Sys,Completing Response to NRC 820619 Request for Info |
ML20081C153 | 5 March 1984 | Advises That,Due to Delays in Delivery & Installation of Auxiliary Safety Instrumentation Panels (Asips),Installation of Six Accident Monitors Addressed in NUREG-0737,Items II.F.1.1 Through II.F.1.6 Will Not Be Completed by 840630 |
ML20082F182 | 23 November 1983 | Forwards Proposed Resolution for Specific Equipment Environ Qualification Deficiencies,Per 831013 Meeting.Master List of safety-related Electrical Equipment & Methodology to Identify Equipment Per 10CFR50.49(b)(2) Also Encl |
ML20087E211 | 8 March 1984 | Submits Addl Info on Generic Ltr 82-33 Schedule Requirements for Emergency Response Capabilities.Vendor of New Computer Sys Requested 1-yr Delay to June 1985 for Delivery,Affecting Schedular Commitments Made to NRC |
ML20087H570 | 30 June 1995 | Rev 0 to Seismic Evaluation Rept |
ML20093D176 | 9 July 1984 | Forwards Update to Schedule & Implementation Status of TMI Action Items in NUREG-0737 |
ML20098H085 | 1 October 1984 | Informs of Current Status of Procurement of New Computer Sys,Which Is Part of Safety Assessment Sys.Revised Schedule for Development,Installation,Startup/Testing & Operation of New Computer Sys Will Be Provided by End of 1984 |
ML20100D970 | 29 March 1985 | Forwards Addl Info Re 830321 Response to Generic Ltr 82-28 Concerning Inadequate Core Cooling Sys Instrumentation,In Response to 850129 Request |
ML20113F657 | 17 January 1985 | Provides Revised Schedule for Installation of Plant Process Computer Sys & Safety Assessment Sys,Equivalent to SPDS (NUREG-0737 Item I.D.2).Schedular Extensions for Completion for Safety Assessment Sys Requested |
ML20127B577 | 7 January 1993 | Responds to NRC Re Violations Noted in Insp Repts 50-266/92-23 & 50-301/92-23 on 921013-1122.Corrective Actions:Administrative Procedure Re Outage Planning, Scheduling & Mgt Being Revised to Require Safety Assessment |