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{
    "query_string": "[[Topic::Reactor Vessel Water Level]] [[Site::Point Beach]]",
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	Issue date	Title
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

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