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Issue date | Title | |
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05000440/FIN-2007005-10 | Adequacy of Reactor Core Isolation Cooling System Surveillance Testing | |
05000440/FIN-2007005-11 | Adequacy of Reactor Core Isolation Cooling System Flow Controller Tuning Procedures | |
05000440/FIN-2016001-01 | Failure to Properly Implement System Operating Instructions to Maintain Control of Reactor Pressure Vessel Level | |
05000440/FIN-2017002-02 | Implementation of Enforcement Guidance Memorandum 11003, Revision 3 | |
05000440/LER-2010-003 | Perry Nuclear Power Plant | |
ENS 45918 | Manual Reactor Scram Due to Loss of Control Rod Drive Charging Water Header Pumps | |
ENS 50551 | Automatic Reactor Scram on Loss of Feedwater | |
ENS 50601 | Automatic Reactor Scram Due to Loss of Feedwater | |
ENS 54185 | Automatic Reactor Scram Due to Main Turbine Trip | |
IR 05000440/1985078 | 8 January 1986 | Insp Rept 50-440/85-78 on 851107-1230.No Violation Noted. Major Areas Inspected:Previous Insp Findings,Preoperational Test Results,Emergency Instruction & Fire Protection & Prevention Program |
IR 05000440/1985082 | 6 December 1985 | Insp Rept 50-440/85-82 on 851118-21.No Violation Noted.Major Areas Inspected:Level of Consistency & Compatibility Between Tech Specs,FSAR,SER,as-built Configurations & Surveillance Requirements |
IR 05000440/1986006 | 24 March 1986 | Insp Rept 50-440/86-06 on 851230-860303.Violations Noted: Inadequate Instructions for Sys Operation,Inadequate Procedural Control safety-related Maint Activity & Failure to Implement Housekeeping/Cleanliness Controls |
IR 05000440/1986009 | 30 April 1986 | Insp Repts 50-440/86-09 & 50-441/86-03 on 860414-17.No Noncompliance or Deviation Noted.Major Areas Inspected: Emergency Preparedness Exercise.Three Weaknesses Re Notification of Alert Not Made within 15 Minutes Noted |
IR 05000440/1986023 | 10 October 1986 | Insp Rept 50-440/86-23 on 860805-0910.Violation Noted: Failure to Identify & Control Operational Status of Plant Instruments Following Maint & During Test & Failure to Identify off-normal Status of Plant Instruments |
IR 05000440/1987016 | 9 December 1987 | Insp Rept 50-440/87-16 on 870813-1019.Violation Noted.Major Areas Inspected:Esfs,Operational Safety,Nonroutine Events, Lers,Startup Testing,Nrc Regional Ofc Requests,Surveillance Testing & Maint Activities |
IR 05000440/1987023 | 2 February 1988 | Insp Rept 50-440/87-23 on 871020-1230.Violations Noted. Major Areas Inspected:Previous Insp Items,Ie Bulletins, 10CFR21 Repts,Regional Ofc Request,Operational Safety, Nonroutine Events,Lers,Physical Security & Maint |
IR 05000440/1988010 | 22 June 1988 | Insp Repts 50-440/88-10 & 50-441/88-05 on 880523-0610.No Violations Noted.Major Areas Inspected:Licensee Implementation of Generic Ltr 83-28 in Areas of Equipment Classification,Vendor Interface & post-maint Testing |
IR 05000440/1993022 | 7 January 1994 | Insp Rept 50-440/93-22 on 931029-1218.Violations Noted. Major Areas Inspected:Licensee Event Rept Followup, Surveillance Observations,Maintenance Observations, Operational Safety Verification & Event Followup |
IR 05000440/1997007 | 24 October 1997 | Insp Rept 50-440/97-07 on 970503-0623.Violations Noted. Major Areas Inspected:Operations,Maintenance,Surveillance, Engineering & Plant Support |
IR 05000440/1997201 | 10 June 1997 | Insp Rept 50-440/97-201 on 970217-0327.Issues Identified Which Challenged Capability of Sys to Perform Complete Scope DBA Mitigation Actions.Major Areas Inspected:Hpcs & Eec Sys |
IR 05000440/2005002 | 5 May 2005 | IR 05000440-05-002, on 01/01/2005 - 03/31/2005; Perry Nuclear Power Plant; Evaluations of Changes, Tests, or Experiments; Equipment Alignment; Operator Performance During Non-Routine Evolutions and Events; Post-Maintenance Testing; Refuelin |
IR 05000440/2005005 | 23 March 2005 | IR 05000440-05-005, on 01/07/2005 - 02/18/2005, Perry Nuclear Power Plant, Unit 1; Special Inspection for Recirculation Pump Downshift Events of December 23, 2004, and January 6, 2005 |
IR 05000440/2006005 | 30 January 2007 | IR 05000440-06-005 on 10/01/2006 - 12/31/2006 for Perry Nuclear Power Plant; Licensed Operation Requalification; Other Activities |
IR 05000440/2007005 | 12 February 2008 | IR 05000440-07-005, on 10/01/2007 - 12/31/2007, Perry, Equipment Alignment, Post-Maintenance Testing, ALARA Planning and Controls; Problem Identification and Resolution, Other Activities |
IR 05000440/2010005 | 1 February 2011 | IR 05000440-10-005, on 10/01/2010 - 12/31/2010, Maintenance Effectiveness, Maintenance Risk Assessments and Emergent Work Control, Surveillance Testing, and Problem Identification and Resolution |
IR 05000440/2016001 | 13 May 2016 | NRC Integrated Inspection Report 05000440/2016001 |
IR 05000440/2017002 | 9 August 2017 | NRC Integrated Inspection Report 05000440/2017002 and Exercise of Enforcement Discretion |
IR 05000440/2017008 | 3 January 2018 | NRC Design Bases Assurance Inspection (Teams) Inspections Report 05000440/2017008 (DRS-N.Feliz-Adorno) |
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 |
Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify | 19 June 2009 | Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify |
L-09-074, License Amendment Request to Provide Consistency in Division 3 Emergency Diesel Generator Start Time Technical Specification Surveillance Requirements | 30 June 2009 | License Amendment Request to Provide Consistency in Division 3 Emergency Diesel Generator Start Time Technical Specification Surveillance Requirements |
L-09-218, Submittal of Technical Specification Bases, Revision 7 | 5 October 2009 | Submittal of Technical Specification Bases, Revision 7 |
L-12-261, Request for Licensing Action to Modify Technical Specification 3.8.1, AC Sources - Operating, to Remove Mode Restrictions on Certain Division 3 Surveillance Requirements | 3 July 2012 | Request for Licensing Action to Modify Technical Specification 3.8.1, AC Sources - Operating, to Remove Mode Restrictions on Certain Division 3 Surveillance Requirements |
L-12-318, License Amendment Request for Adoption of TSTF-275-A, Revision 0, Clarify Requirement for EDG Start Signal on RPV Level - Low, Low, Low During RPV Cavity Flood-up, and TSTF-300-A, Revision 0 | 5 September 2012 | License Amendment Request for Adoption of TSTF-275-A, Revision 0, Clarify Requirement for EDG Start Signal on RPV Level - Low, Low, Low During RPV Cavity Flood-up, and TSTF-300-A, Revision 0 |
L-14-106, License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b | 25 March 2014 | License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b |
L-14-325, Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325) | 27 March 2015 | Issuance of Amendment Concerning Safety Limit Critical Power Ratio Values (TAC No. MF5007)(L-14-325) |
L-16-083, License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3 | 15 March 2016 | License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3 |