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 Issue dateTitle
IR 05000266/202200424 January 2023Integrated Inspection Report 05000266/2022004 and 05000301/2022004
L-2022-121, Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-0229 July 2022Exemption Request, License Amendment Request and Revised Response in Support of a Risk-informed Resolution of Generic Letter 2004-02
ML21102A3482 April 2021Update to Final Safety Analysis Report, Chapter 7, Instrumentation and Control
IR 05000266/202000113 May 2020Integrated Inspection Report 05000266/2020001 and 05000301/2020001
ML17363A14521 December 2017Response 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
NRC 2017-0041, to 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 Reactors21 August 2017to 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 Reactors
NRC 2017-0028, 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 Reactors.23 June 2017License Amendment Request 286, Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.
ML16251A1561 September 2016Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control
NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control1 September 2016Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control
NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2 August 2010License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
NRC 2010-0105, License Amendment Request 261, Supplement 6 Extended Power Uprate28 July 2010License Amendment Request 261, Supplement 6 Extended Power Uprate
NRC 2010-0022, License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate25 February 2010License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate
ML14342A1509 December 2009Nextera Energy Point Beach, LLC Point Beach Nuclear Plant, Units 1 and 2, Revision 53 of Emergency Plan
NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate8 December 2009License Amendment Request 261, Supplement 3 Extended Power Uprate
ML0806704197 March 2008CDBI Findings
ML05348012222 December 2005Appendix a - Technical Specifications
ML0514002688 October 2004Enclosures V & VI Point Beach Revised EAL Submittal, Justification Matrix Reference Material
ML04231052313 August 2004Technical Specifications, Relocation of Requirements for Hydrogen Monitors
ML0510500459 April 2004RCE 254, Potential Loss of Hot Leg Vent Path During Nozzle Dam Installation.
ML04042042430 January 2004Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process
NRC 2003-0012, Emergency Plan Implementing Procedure Revisions, Point Beach Nuclear Plant, Units 1 & 27 February 2003Emergency Plan Implementing Procedure Revisions, Point Beach Nuclear Plant, Units 1 & 2
ML0222803548 August 2002DAEC Emergency Planning Department Procedure Transmittal Acknowledgment Memo
ML0207304082 February 2002Initial SRO Examination 02/2002
ML99363048223 December 1999Revised Epips, Including Revision 25 to EPIP 1.3, Revision 18 to EPIP 2.1, Revision 29 to EPIP 4.1, Revision 14 to EPIP 4.2, Revision 22 to EPIP 4.3, Revision 0 to EPIP 4.7, Revision 12 to EPIP 5.1and Revision 11 to EPIP 5.2. with 12/23/99
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
NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with31 December 19981998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with
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
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
ML20138K31231 January 1997Rev 43 to RP 1A, Preparation for Refueling
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 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 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
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 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
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 10.231 August 1995Forwards 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
ML20087H57030 June 1995Rev 0 to Seismic Evaluation Rept
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 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
ML07104001728 April 199459 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
IR 05000266/199301522 December 1993Insp 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
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
ML20127B5777 January 1993Responds 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
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)
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
ML20067E04831 January 1991Responds 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
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
ML20151R6772 August 1988Safety Evaluation Granting Request for Relief from ASME Code,Section XI Evaluation Requirements
ML20148T59725 January 1988Forwards Requests for Inservice Insp Relief from ASME Section XI for Second 10-yr Insp Interval for Plant.Approval Requested by Sept 1988 to Allow Time Prior to Spring 1989 Unit 1 Refueling During Which Time Exams Scheduled.Fee Paid
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