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 Issue dateTitle
05000333/LER-2013-0061 OF 6
ENS 41987Automatic Reactor Scram on Low Reactor Vessel Water Level During Planned Maintenance
ENS 50532High Pressure Core Injection Degraded Accident Mitigation Capability
IR 05000333/198502228 September 1985Insp Rept 50-333/85-22 on 850715-0831.No Violation Noted. Major Areas Inspected:Ler Review,Operational Safety Verification,Surveillance Observations,Maint Observations & Followup on Plant Trips
IR 05000333/198701312 May 1987Insp Rept 50-333/87-13 on 870406-09.No Violations or Deviations Noted.Major Areas Inspected:Procedure Review,Test Witnessing & Preliminary Results Evaluation of Periodic Containment Integrated Leak Rate Test.Tables Encl
IR 05000333/19870263 February 1988Insp Rept 50-333/87-26 on 871201-880111.Violations Noted. Major Areas Inspected:Operational Safety Review,Surveillance & Maint Observations,Followup of Plant Trip,Ie Bulletin & ESF Actuation & Review of Missed Surveillance Tests
IR 05000333/19930828 December 1993Insp Rept 50-333/93-82 on 931004-21.No Violations Noted. Major Areas Inspected:Mgt Programs & Oversight,Assessment/ Improvement Programs,Problem Identification & Resolution & Engineering & Technical Support
IR 05000333/199800318 August 1998Insp Rept 50-333/98-03 on 980601-0712.No Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support
IR 05000333/199800410 September 1998Insp Rept 50-333/98-04 on 980713-0823.Violations Noted.Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support.Rept Also Covers Results of Announced Security & Emergency Prepardness Insps by Region Based Specialists
IR 05000333/199800810 February 1999Insp Rept 50-333/98-08 on 981123-990110.No Violations Noted. Major Areas Inspected:Operations,Egineering,Maintenance & Plant Support
IR 05000333/199900418 June 1999Insp Rept 50-333/99-04 on 990412 to 0529.Non Cited Violations Noted.Major Areas Inspected:Operations,Maint & Engineering
IR 05000333/200400330 July 2004IR 05000333-04-003 on 04/01/2004 - 06/30/2004 for James A. FitzPatrick Nuclear Power Plant; Licensed Operator Requalification
IR 05000333/20040048 November 2004IR 05000333-04-004; on 07/01/2004 - 09/30/2004; James A. FitzPatrick Nuclear Power Plant; Fire Protection
IR 05000333/20040052 February 2005IR 05000333-04-005, on 10/01/2004 -12/31/2004, James A. FitzPatrick Nuclear Power Plant; Post Maintenance Testing, Problem Identification and Resolution, Event Follow-up
IR 05000333/200500526 October 2005IR 05000333-05-005; 07/01/2005 - 09/30/2005; James A. FitzPatrick Nuclear Power Plant; Event Response, and Cross Cutting Aspects of Findings
IR 05000333/20050061 February 2006IR 05000333-05-006; 10/01/2005 - 12/31/2005; James A. FitzPatrick Nuclear Power Plant; Evaluation of Changes, Tests or Experiments, Maintenance Effectiveness, and Maintenance Risk Assessment and Emergent Work Control
IR 05000333/202000210 August 2020Integrated Inspection Report 05000333/2020002
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
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
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
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 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
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 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
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 1996-65, 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 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown5 December 1997Recent 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, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
JAFP-01-0133, ITS: 3.3.4.1 Anticipated Transient Without Scram Recirulation Pump Trip (ATWS-RPT) Instrumentation7 April 1995ITS: 3.3.4.1 Anticipated Transient Without Scram Recirulation Pump Trip (ATWS-RPT) Instrumentation
JAFP-02-0098, Part 7 of 7, James A. FitzPatrick Nuclear Power Plant - Revision J to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications, Bases26 April 2002Part 7 of 7, James A. FitzPatrick Nuclear Power Plant - Revision J to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications, Bases
JAFP-02-0124, Revision K to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications11 June 2002Revision K to Proposed Technical Specification Change (License Amendment) Conversion to Improved Standard Technical Specifications
JAFP-04-0083, Proposed License Amendment Re Safety Limit Minimum Critical Power Ratio4 June 2004Proposed License Amendment Re Safety Limit Minimum Critical Power Ratio
JAFP-04-0158, Follow-up Response to Request for Additional Information and Revision to Proposed License Amendment to Safety Limit Minimum Critical Power Ratio (SLMCPR)27 September 2004Follow-up Response to Request for Additional Information and Revision to Proposed License Amendment to Safety Limit Minimum Critical Power Ratio (SLMCPR)
JAFP-09-0086, Application for Amendment for James A. FitzPatrick Nuclear Power Plant to Modify the Technical Specifications Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure - High Function31 July 2009Application for Amendment for James A. FitzPatrick Nuclear Power Plant to Modify the Technical Specifications Requirements for Testing of the Shutdown Cooling System Isolation, Reactor Pressure - High Function
JAFP-10-0050, Proposed Change to the Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio21 April 2010Proposed Change to the Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio
JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal6 April 20112011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
JAFP-11-0088, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program in Accordance with TSTF-425, Revision 3, James A. F22 July 2011Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program in Accordance with TSTF-425, Revision 3, James A. FitzP
JAFP-13-0115, Application to Revise Technical Specifications for Technical Specification Low Pressure Safety Limit8 October 2013Application to Revise Technical Specifications for Technical Specification Low Pressure Safety Limit
JAFP-14-0047, Proposed Change to Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio1 May 2014Proposed Change to Technical Specification Concerning the Safety Limit Minimum Critical Power Ratio
JAFP-15-0047, 2015 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal8 April 20152015 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
JAFP-17-0051, LER 17-03-00 for FitzPatrick Regarding Inadvertent Isolation of the High Pressure Coolant Injection System5 June 2017LER 17-03-00 for FitzPatrick Regarding Inadvertent Isolation of the High Pressure Coolant Injection System
JAFP-17-0083, Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events29 August 2017James a Fitzpatrick, Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
JAFP-17-0093, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22 October 2017Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
JAFP-18-0012, Supplemental Response Concerning License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 222 January 2018Supplemental Response Concerning License Amendment Request to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
JAFP-19-0105, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)...6 November 2019Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (Rwcu)...
JAFP-20-0026, Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation31 March 2020Response to Request for Additional Information to Support Review of a License Amendment Request to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation
JAFP-21-0022, Technical Requirements Manual Specifications - Redacted29 March 2022Technical Requirements Manual Specifications - Redacted
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