Reactor Water Recirculation
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creation date: 2025-12-08T17:59:57-05:00
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Reactor Water Recirculation
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RWR
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ENS 56373
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IR 05000333/2023004
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ML20210N234
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BSEP-87-0065, Annual Rept of Facility Changes,Tests & Experiments,1986
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IR 05000254/1985019
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IR 05000333/2017003
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IR 05000333/2022004
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JAFP-92-0470, Ja Fitzpatrick Nuclear Power Plant Annual Summary of Changes,Tests & Experiments for 1990
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JAFP-18-0113, Fifth Ten-Year Inservice Inspection Interval Program Plan
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JAFP-07-0019, License Renewal Application, Amendment 9
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LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 5, Reactor Coolant System and Connected Systems
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JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.
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RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 5.0 - Reactor Coolant System and Connected Systems
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RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected Systems
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RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 5 - Reactor Coolant System and Connected Systems
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RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 5 - Reactor Coolant System and Connected Systems
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IR 05000354/2006003
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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, Bases
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IR 05000333/2019010
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IR 05000333/2015003
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IR 05000333/2020001
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JAFP-17-0093, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2
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IR 05000259/2006006
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IR 05000333/2002008
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IR 05000333/2010005
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IR 05000259/2007009
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NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 12
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IR 05000259/2006002
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IR 05000333/1989008
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PY-CEI-NRR-0106, Responds to NRC Requesting Addl Copies of Inservice Testing Program for Pumps & Valves.Program & Drawings Encl.W/O Encl
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IR 05000333/1997002
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JAFP-99-0171, Forwards Revised Ja FitzPatrick Nuclear Power Plant 1999 FSAR Update. Update Also Includes Changes to Chapter 17, QA Program Which Described in Attachment 1.No Commitments Contained in Ltr
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IR 05000333/2014003
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AECM-84-0205, Submits Addl Response to IE Bulletin 80-24, Prevention of Damage Due to Water Leakage Inside Containment. Insp & Surveillance of Containment Sumps,Drywell,Piping & Closed Coolant Water Sys Discussed.Action Completed
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IR 05000259/2004007
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PY-CEI-NRR-0302, Forwards Revised Vibration & Thermal Expansion Test Program. Categories of Proposed Changes Listed
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IR 05000333/2016001
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NLS2017062, Licensee Guarantees of Payment of Deferred Premiums
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JAFP-94-0150, Annual Summary of Changes,Tests & Experiments for 1993
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IR 05000333/2003008
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JAFP-07-0116, Fourth Interval Inservice Testing Program for Pumps and Valves
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IR 05000458/2013003
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IR 05000259/2004009
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RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 9 - Auxiliary Systems
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PY-CEI-NRR-0441, Forwards Info Re Status of Pending Changes to FSAR, Correcting Editorial Errors & Typos.Pending FSAR Change Pages Encl
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RS-17-126, Quad Cities Nuclear Power Station, Units 1 & 2, Revision 14 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems
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JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with
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347 Modified Stainless Steel.Electrochemical Potential Monitoring Sys Installed in Reactor Water Recirculation Sys
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IR 05000259/2005008
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IR 05000259/2003011
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BECO-89-094, Requests Exemption from Primary Containment Leakage Testing Requirements of 10CFR50,App J for Local Leak Rate Tests of Shutdown Cooling Suction Isolation Valves,Reactor Bldg Closed Cooling Water Isolation Valve & Drywell Head
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ML17298B250
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CNL-22-002, Request for Relief from American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, in Accordance with 10 CFR 50.55a(g)(5)(iii) and 50.55a(g)(6) (BFN-2-ISI-003)
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ML20128K008
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RS-16-196, Clinton - Updated Safety Analysis Report (Usar), Revision 18, Chapter 9 - Auxiliary Systems
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JAFP-08-0038, Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout
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JPN-99-020, Submits Response to RAI Re ISI Program Relief Requests for Second 10-yr Interval Closeout & Summary Rept,Per 990426 Telcon with Nrc.Info Provided to Clarify or Withdraw Individual Relief Requests Contained in Summary Rept
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IR 05000333/2005005
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IR 05000333/2014004
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IR 05000333/2023003
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IR 05000333/2012003
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ML20207B602
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JAFP-09-0072, Response to Request for Additional Information Regarding: Emergency License Amendment Request Application for Technical Specification 3.8.1 Required Action B.4 Completion Time
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IR 05000333/2005003
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ML062230063
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JAFP-06-0110, James A.Fitzpatrick, License Renewal Application Drawing List
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NLS2018037, Licensee Guarantees of Payment of Deferred Premiums
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IR 05000271/1999001
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IR 05000333/2011004
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IR 05000333/2015002
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IR 05000333/2013004
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IR 05000333/2017004
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IR 05000333/2015004
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NLS2017058, Nebraska Public Power District 2016 Financial Report
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IR 05000333/2019004
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BVY-97-137, Forwards Response to 971009 RAI Re Plans for Implementing ASME Code Case N560 at Vermont Yankee Nuclear Power Station
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JAFP-92-0598, Ja Fitzpatrick Nuclear Power Plant,Annual Summary of Changes,Tests & Experiments for 1991
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JAFP-18-0078, Fifth Ten-Year Interval Inservice Testing Program Plan
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IR 05000333/2015001
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JAFP-95-0176, Annual Summary of Changes,Tests & Experiments for 1994. W/
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IR 05000333/1988015
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IR 05000333/2017001
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4 TS 3.6.2.5 and TS 3.6.3.2, Using the Consolidated Line.
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ML20195C416
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ML17226A133
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JAFP-11-0046, 2011 Updated Final Safety Analysis Report, Technical Specification Bases and Technical Requirements Manual Changes Transmittal
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ML20101F841
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ML19276G313
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ML20071G926
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IR 05000333/2020002
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IR 05000333/2023002
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RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
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IR 05000333/2023001
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ML19208A312
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IR 05000333/2012005
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ML20084J589
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ML20084D332
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ML20065C651
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ML072560047
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ML20080J761
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ML20094G960
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ML18025B137
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JAFP-05-0069, Summary of Plant Changes, Tests, and Experiments for 2003 and 2004 as Required by 10 CFR 50.59 and 10 CFR 72.48, and Summary of Commitment Changes for 2003 and 2004
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ML20199F279
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ML20023A856
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IR 05000333/2010004
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IR 05000259/2004006
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ML19354D704
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IR 05000333/2016003
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page: https://kanterella.com/IR_05000333/2016003
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ML043090143
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IR 05000333/2003010
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page: https://kanterella.com/IR_05000333/2003010
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SNRC-1904, Forwards 10CFR50.59 Rept for Period from Jan-Dec 1991
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wiki page sort key: SNRC-1904, Forwards 10CFR50.59 Rept for Period from Jan-Dec 1991

ML17010A361
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ML20217D996
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Degradation Mechanism Evaluation & Results of Element & Segment Risk Rankings.Util Intends to Submit Revised ISI Program Following NRC Review of Evaluations & Risk Ranking,As Stated in Ltr
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label: BVY-97-105, Provides NRC W/Degradation Mechanism Evaluation & Results of Element & Segment Risk Rankings.Util Intends to Submit Revised ISI Program Following NRC Review of Evaluations & Risk Ranking,As Stated in Ltr
page: https://kanterella.com/BVY-2D97-2D105-2C_Provides_NRC_W/Degradation_Mechanism_Evaluation_-26_Results_of_Element_-26_Segment_Risk_Rankings.Util_Intends_to_Submit_Revised_ISI_Program_Following_NRC_Revie…
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wiki page sort key: BVY-97-105, Provides NRC W/Degradation Mechanism Evaluation & Results of Element & Segment Risk Rankings.Util Intends to Submit Revised ISI Program Following NRC Review of Evaluations & Risk Ranking,As Stated in Ltr

ML21307A184
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RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 9 - Auxiliary Systems
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page: https://kanterella.com/RS-2D13-2D009-2C_Clinton-2C_Unit_1-2C_Updated_Safety_Analysis_Report-2C_Revision_15-2C_Chapter_9_-2D_Auxiliary_Systems
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ML20012D009
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IR 05000333/2016002
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page: https://kanterella.com/IR_05000333/2016002
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IR 05000333/2014005
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page: https://kanterella.com/IR_05000333/2014005
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IR 05000259/2008005
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page: https://kanterella.com/IR_05000259/2008005
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IR 05000333/2011002
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page: https://kanterella.com/IR_05000333/2011002
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ML18022A342
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ML18025B913
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IR 05000333/2012002
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page: https://kanterella.com/IR_05000333/2012002
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ML18298A004
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page: https://kanterella.com/ML18298A004
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wiki page sort key: ML18298A004

JAFP-10-0079, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Low Pressure Coolant Injection Inverter
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page: https://kanterella.com/JAFP-2D10-2D0079-2C_Application_for_Amendment_to_Modify_the_Technical_Specifications_Requirements_for_Testing_of_Low_Pressure_Coolant_Injection_Inverter
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wiki page sort key: JAFP-10-0079, Application for Amendment to Modify the Technical Specifications Requirements for Testing of Low Pressure Coolant Injection Inverter

ML17252A842
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ML18038B629
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JAFP-02-0008, December 2001 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
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page: https://kanterella.com/JAFP-2D02-2D0008-2C_December_2001_Monthly_Operating_Report_for_James_A._FitzPatrick_Nuclear_Power_Plant
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wiki page sort key: JAFP-02-0008, December 2001 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant

IR 05000333/1987026
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page: https://kanterella.com/IR_05000333/1987026
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wiki page sort key: IR 05000333/1987026

ML20262G664
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ML21286A513
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IR 05000333/2022003
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05000458/FIN-2013003-02
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JAFP-17-0085, High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic
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page: https://kanterella.com/JAFP-2D17-2D0085-2C_High_Frequency_Confirmation_Report_for_March_12-2C_2012-2C_Information_Request_Pursuant_to_10_CFR_50.54-28f-29_Regarding_Recommendation_2.1-2C_Seismic
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wiki page sort key: JAFP-17-0085, High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic

IR 05000333/2018002
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wiki page sort key: IR 05000333/2018002

IR 05000333/2014002
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page: https://kanterella.com/IR_05000333/2014002
wiki namespace: 0
wiki page content language: en
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wiki page sort key: IR 05000333/2014002

IR 05000333/2012007
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page: https://kanterella.com/IR_05000333/2012007
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wiki page content language: en
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wiki page sort key: IR 05000333/2012007

IR 05000333/2003005
type: Subject
page: https://kanterella.com/IR_05000333/2003005
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000333/2003005

NG-03-0642, August 2003 Monthly Operating Report for Duane Arnold Energy Center
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page: https://kanterella.com/NG-2D03-2D0642-2C_August_2003_Monthly_Operating_Report_for_Duane_Arnold_Energy_Center
wiki namespace: 0
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wiki page sort key: NG-03-0642, August 2003 Monthly Operating Report for Duane Arnold Energy Center

IR 05000333/2001012
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page: https://kanterella.com/IR_05000333/2001012
wiki namespace: 0
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wiki page sort key: IR 05000333/2001012

ML20151W024
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page: https://kanterella.com/ML20151W024
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wiki page sort key: ML20151W024

ML20262G660
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wiki page sort key: ML20262G660

ML20245H375
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ML18018A780
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PNO-III-83-100, on 831020,ultrasonic Testing Identified One Crack & Ten Crack Indications in Unit 2 Primary Sys Piping, Including Seven Indications in Reactor Water Recirculation Sys.Licensee Intends to Issue News Announcement
type: Subject
page: https://kanterella.com/PNO-2DIII-2D83-2D100-2C_on_831020-2Cultrasonic_Testing_Identified_One_Crack_-26_Ten_Crack_Indications_in_Unit_2_Primary_Sys_Piping-2C_Including_Seven_Indications_in_Reactor_Wate…
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wiki page sort key: PNO-III-83-100, on 831020,ultrasonic Testing Identified One Crack & Ten Crack Indications in Unit 2 Primary Sys Piping, Including Seven Indications in Reactor Water Recirculation Sys.Licensee Intends to Issue News Announcement

IR 05000333/1989018
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page: https://kanterella.com/IR_05000333/1989018
wiki namespace: 0
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wiki page sort key: IR 05000333/1989018

ML20082B854
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wiki page sort key: ML20082B854

IR 05000333/2024002
type: Subject
page: https://kanterella.com/IR_05000333/2024002
wiki namespace: 0
wiki page content language: en
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wiki page sort key: IR 05000333/2024002

IR 05000440/2018011
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page: https://kanterella.com/IR_05000440/2018011
wiki namespace: 0
wiki page content language: en
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wiki page sort key: IR 05000440/2018011

ML20084U925
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wiki page sort key: ML20084U925

ML19312E102
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wiki page sort key: ML19312E102

JAFP-91-0105, Monthly Operating Rept for Jan 1991 for Ja FitzPatrick Nuclear Power Plant
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page: https://kanterella.com/JAFP-2D91-2D0105-2C_Monthly_Operating_Rept_for_Jan_1991_for_Ja_FitzPatrick_Nuclear_Power_Plant
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wiki page sort key: JAFP-91-0105, Monthly Operating Rept for Jan 1991 for Ja FitzPatrick Nuclear Power Plant

ML13079A022
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wiki page sort key: ML13079A022

PNO-III-07-009, A: Perry: Update to Unexpected Reactor Shutdown Exceeding 72 Hours Due to Problem with Reactor Recirculation Pump Motor
type: Subject
page: https://kanterella.com/PNO-2DIII-2D07-2D009-2C_A-3A_Perry-3A_Update_to_Unexpected_Reactor_Shutdown_Exceeding_72_Hours_Due_to_Problem_with_Reactor_Recirculation_Pump_Motor
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wiki page sort key: PNO-III-07-009, A: Perry: Update to Unexpected Reactor Shutdown Exceeding 72 Hours Due to Problem with Reactor Recirculation Pump Motor

JAFP-02-0064, Revised November 2001 Monthly Operating Report for James A. FitzPatrick
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wiki page sort key: JAFP-02-0064, Revised November 2001 Monthly Operating Report for James A. FitzPatrick

ML20261G506
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page: https://kanterella.com/ML20261G506
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wiki page sort key: ML20261G506

JAFP-03-0169, November 2003 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
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page: https://kanterella.com/JAFP-2D03-2D0169-2C_November_2003_Monthly_Operating_Report_for_James_A._FitzPatrick_Nuclear_Power_Plant
wiki namespace: 0
wiki page content language: en
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wiki page sort key: JAFP-03-0169, November 2003 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant

IR 05000333/2001013
type: Subject
page: https://kanterella.com/IR_05000333/2001013
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000333/2001013

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 Function
type: Subject
page: https://kanterella.com/JAFP-2D09-2D0086-2C_Application_for_Amendment_for_James_A._FitzPatrick_Nuclear_Power_Plant_to_Modify_the_Technical_Specifications_Requirements_for_Testing_of_the_Shutdown_Coolin…
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wiki page sort key: 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 Function

ML20207E666
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wiki page sort key: ML20207E666

ML20024A067
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wiki page sort key: ML20024A067

05000333/LER-2001-002
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page: https://kanterella.com/05000333/LER-2D2001-2D002
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-2001-002

ML20197J057
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page: https://kanterella.com/ML20197J057
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system: Reactor Water Recirculation
wiki page sort key: ML20197J057

JAFP-03-0139, September 2003 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
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page: https://kanterella.com/JAFP-2D03-2D0139-2C_September_2003_Monthly_Operating_Report_for_James_A._FitzPatrick_Nuclear_Power_Plant
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wiki page sort key: JAFP-03-0139, September 2003 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant

05000333/LER-2001-004
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page: https://kanterella.com/05000333/LER-2D2001-2D004
wiki namespace: 0
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wiki page sort key: 05000333/LER-2001-004

ML18023A467
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JAFP-02-0086, March 2002 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
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wiki page sort key: JAFP-02-0086, March 2002 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant

JAFP-02-0107, April 2002 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant
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wiki page sort key: JAFP-02-0107, April 2002 Monthly Operating Report for James A. FitzPatrick Nuclear Power Plant

05000333/FIN-2017003-01
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wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: 05000333/FIN-2017003-01

JAFP-14-0123, Response to Request for Additional Information (RAI) for Low Pressure Safety Limit License Amendment
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page: https://kanterella.com/JAFP-2D14-2D0123-2C_Response_to_Request_for_Additional_Information_-28RAI-29_for_Low_Pressure_Safety_Limit_License_Amendment
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wiki page sort key: JAFP-14-0123, Response to Request for Additional Information (RAI) for Low Pressure Safety Limit License Amendment

ML19261D862
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JAFP-10-0033, Attachment 2 to JAFP-10-0033, Calculation JAF-CALC-NBS-02052, Revision 4
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wiki page sort key: JAFP-10-0033, Attachment 2 to JAFP-10-0033, Calculation JAF-CALC-NBS-02052, Revision 4

JPN-88-030, Forwards Addl Info Re Plant Alternate Rod Insertion & Recirculation Pump Trip Designs,Per ATWS Rule W/21 Oversize Drawings
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page: https://kanterella.com/JPN-2D88-2D030-2C_Forwards_Addl_Info_Re_Plant_Alternate_Rod_Insertion_-26_Recirculation_Pump_Trip_Designs-2CPer_ATWS_Rule_W/21_Oversize_Drawings
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wiki page sort key: JPN-88-030, Forwards Addl Info Re Plant Alternate Rod Insertion & Recirculation Pump Trip Designs,Per ATWS Rule W/21 Oversize Drawings

ML19225A284
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ML062140267
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IR 05000341/1989016
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page: https://kanterella.com/IR_05000341/1989016
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wiki page sort key: IR 05000341/1989016

05000333/FIN-2010005-02
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05000333/FIN-2015001-02
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wiki page sort key: 05000333/FIN-2015001-02

ML20009C139
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wiki page sort key: ML20009C139

ML20082B852
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page: https://kanterella.com/ML20082B852
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wiki page sort key: ML20082B852

JPN-91-032, Forwards Application for Amend to License DPR-59,changing TS Tables 3.2-7 & 4.2-7 to Reflect Change in Reactor Water Recirculation Pump Trip Logic & Increasing Min Number of Operable Channels from One to Two
type: Subject
page: https://kanterella.com/JPN-2D91-2D032-2C_Forwards_Application_for_Amend_to_License_DPR-2D59-2Cchanging_TS_Tables_3.2-2D7_-26_4.2-2D7_to_Reflect_Change_in_Reactor_Water_Recirculation_Pump_Trip_Logic_-2…
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system: Reactor Water Recirculation
wiki page sort key: JPN-91-032, Forwards Application for Amend to License DPR-59,changing TS Tables 3.2-7 & 4.2-7 to Reflect Change in Reactor Water Recirculation Pump Trip Logic & Increasing Min Number of Operable Channels from One to Two

ML063100442
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wiki page sort key: ML063100442

IR 05000333/2004006
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page: https://kanterella.com/IR_05000333/2004006
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system: Reactor Water Recirculation
wiki page sort key: IR 05000333/2004006

JAFP-07-0079, License Renewal Application, Amendment 12
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page: https://kanterella.com/JAFP-2D07-2D0079-2C_License_Renewal_Application-2C_Amendment_12
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wiki page sort key: JAFP-07-0079, License Renewal Application, Amendment 12

JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant
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page: https://kanterella.com/JAFP-2D98-2D0168-2C_Monthly_Operating_Rept_for_Apr_1998_for_Ja_FitzPatrick_Nuclear_Power_Plant
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wiki page sort key: JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant

JAFP-89-0586, Monthly Operating Rept for Jul 1989 for Ja Fitzpatrick Nuclear Power Plant
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page: https://kanterella.com/JAFP-2D89-2D0586-2C_Monthly_Operating_Rept_for_Jul_1989_for_Ja_Fitzpatrick_Nuclear_Power_Plant
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wiki page sort key: JAFP-89-0586, Monthly Operating Rept for Jul 1989 for Ja Fitzpatrick Nuclear Power Plant

IR 05000333/2004002
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page: https://kanterella.com/IR_05000333/2004002
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wiki page sort key: IR 05000333/2004002

IR 05000259/2006007
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page: https://kanterella.com/IR_05000259/2006007
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: IR 05000259/2006007

ML18039A793
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wiki page sort key: ML18039A793

ML20266E990
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page: https://kanterella.com/ML20266E990
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wiki page sort key: ML20266E990

05000333/FIN-2012003-02
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page: https://kanterella.com/05000333/FIN-2D2012003-2D02
wiki namespace: 0
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wiki page sort key: 05000333/FIN-2012003-02

ML14056A268
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page: https://kanterella.com/ML14056A268
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wiki page sort key: ML14056A268

ML21286A376
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page: https://kanterella.com/ML21286A376
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wiki page sort key: ML21286A376

ML20090H100
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page: https://kanterella.com/ML20090H100
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wiki page sort key: ML20090H100

05000333/FIN-2013004-01
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wiki namespace: 0
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wiki page sort key: 05000333/FIN-2013004-01

IR 05000333/2002003
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page: https://kanterella.com/IR_05000333/2002003
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: IR 05000333/2002003

ML20084K698
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page: https://kanterella.com/ML20084K698
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wiki page sort key: ML20084K698

ML18038B183
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page: https://kanterella.com/ML18038B183
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wiki page sort key: ML18038B183

IR 05000333/2021002
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page: https://kanterella.com/IR_05000333/2021002
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: IR 05000333/2021002

JAFP-02-0199, September 2002 Monthly Operating Report for James A. FitzPatrick
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page: https://kanterella.com/JAFP-2D02-2D0199-2C_September_2002_Monthly_Operating_Report_for_James_A._FitzPatrick
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wiki page sort key: JAFP-02-0199, September 2002 Monthly Operating Report for James A. FitzPatrick

ML19344B290
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page: https://kanterella.com/ML19344B290
wiki namespace: 0
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wiki page sort key: ML19344B290

ML21364A043
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page: https://kanterella.com/ML21364A043
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wiki page sort key: ML21364A043

ML20261M073
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page: https://kanterella.com/ML20261M073
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wiki page sort key: ML20261M073

IR 05000333/2011003
type: Subject
page: https://kanterella.com/IR_05000333/2011003
wiki namespace: 0
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wiki page sort key: IR 05000333/2011003

ML063560224
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page: https://kanterella.com/ML063560224
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wiki page sort key: ML063560224

ML21286A268
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page: https://kanterella.com/ML21286A268
wiki namespace: 0
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wiki page sort key: ML21286A268

ML20116N688
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wiki page sort key: ML20116N688

ML20084J917
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wiki page sort key: ML20084J917

ML20115G058
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page: https://kanterella.com/ML20115G058
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wiki page sort key: ML20115G058

ML18039A591
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page: https://kanterella.com/ML18039A591
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wiki page sort key: ML18039A591

ML21286A416
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page: https://kanterella.com/ML21286A416
wiki namespace: 0
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wiki page sort key: ML21286A416

HL-5107, Forwards Response to NRC Re Violations Noted in Insp Rept 50-366/95-26.Corrective Actions:Repaired Aforementioned Deficient Conditions
type: Subject
page: https://kanterella.com/HL-2D5107-2C_Forwards_Response_to_NRC_Re_Violations_Noted_in_Insp_Rept_50-2D366/95-2D26.Corrective_Actions-3ARepaired_Aforementioned_Deficient_Conditions
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: HL-5107, Forwards Response to NRC Re Violations Noted in Insp Rept 50-366/95-26.Corrective Actions:Repaired Aforementioned Deficient Conditions

JAFP-02-0226, November 2002 Monthly Operating Report for James A.Fitzpatrick Nuclear Power Plant
type: Subject
page: https://kanterella.com/JAFP-2D02-2D0226-2C_November_2002_Monthly_Operating_Report_for_James_A.Fitzpatrick_Nuclear_Power_Plant
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: JAFP-02-0226, November 2002 Monthly Operating Report for James A.Fitzpatrick Nuclear Power Plant

NUREG-1905, Safety Evaluation Report Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant
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page: https://kanterella.com/NUREG-2D1905-2C_Safety_Evaluation_Report_Related_to_the_License_Renewal_of_James_A._FitzPatrick_Nuclear_Power_Plant
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: NUREG-1905, Safety Evaluation Report Related to the License Renewal of James A. FitzPatrick Nuclear Power Plant

05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System
type: Subject
page: https://kanterella.com/05000333/LER-2D2023-2D001-2C_Primary_Containment_Isolation_System_Isolation_Due_to_Initiation_of_Main_Condenser_Fire_Protection_Foam_System
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system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-2023-001, Primary Containment Isolation System Isolation Due to Initiation of Main Condenser Fire Protection Foam System

ML22278A835
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page: https://kanterella.com/ML22278A835
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: ML22278A835

ML21286A516
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page: https://kanterella.com/ML21286A516
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wiki page sort key: ML21286A516

ML20261L427
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page: https://kanterella.com/ML20261L427
wiki namespace: 0
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wiki page sort key: ML20261L427

ML20261D106
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page: https://kanterella.com/ML20261D106
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wiki page sort key: ML20261D106

ML20261D109
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page: https://kanterella.com/ML20261D109
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: ML20261D109

ML20261D113
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page: https://kanterella.com/ML20261D113
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system: Reactor Water Recirculation
wiki page sort key: ML20261D113

ML20261D112
type: Subject
page: https://kanterella.com/ML20261D112
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: ML20261D112

O Prior Evaluation Required by 10CFR50.59.Cause Not Stated. Mod of Control Procedures Revised
type: Subject
label: 05000333/LER-1989-011-01, :on 890531,plugging of Non safety-related Floor Drains in Emergency Diesel Generator Rooms Performed W/O Prior Evaluation Required by 10CFR50.59.Cause Not Stated. Mod of Control Procedures Revised
page: https://kanterella.com/05000333/LER-2D1989-2D011-2D01-2C_-3Aon_890531-2Cplugging_of_Non_safety-2Drelated_Floor_Drains_in_Emergency_Diesel_Generator_Rooms_Performed_W/O_Prior_Evaluation_Required_by_10C…
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1989-011-01, :on 890531,plugging of Non safety-related Floor Drains in Emergency Diesel Generator Rooms Performed W/O Prior Evaluation Required by 10CFR50.59.Cause Not Stated. Mod of Control Procedures Revised

LER-1987-018, :on 871108,reactor Tripped from High Neutron Flux Due to Erratic Operation of Reactor Water Recirculation Pump Speed Controller.Caused by Malfunction in Pump Speed Controller Switch.Controller Replaced
type: Subject
label: 05000333/LER-1987-018, :on 871108,reactor Tripped from High Neutron Flux Due to Erratic Operation of Reactor Water Recirculation Pump Speed Controller.Caused by Malfunction in Pump Speed Controller Switch.Controller Replaced
page: https://kanterella.com/05000333/LER-2D1987-2D018-2C_-3Aon_871108-2Creactor_Tripped_from_High_Neutron_Flux_Due_to_Erratic_Operation_of_Reactor_Water_Recirculation_Pump_Speed_Controller.Caused_by_Malfun…
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1987-018, :on 871108,reactor Tripped from High Neutron Flux Due to Erratic Operation of Reactor Water Recirculation Pump Speed Controller.Caused by Malfunction in Pump Speed Controller Switch.Controller Replaced

JPN-87-035, Forwards Insp Summary of Igscc,Per Util 861028 Commitment. Welds Classified According to NUREG-0313,Rev 2.Specific Insp Plans Will Be Addressed Prior to Next Scheduled Refueling Outage.Two Oversize Drawings Encl
type: Subject
page: https://kanterella.com/JPN-2D87-2D035-2C_Forwards_Insp_Summary_of_Igscc-2CPer_Util_861028_Commitment._Welds_Classified_According_to_NUREG-2D0313-2CRev_2.Specific_Insp_Plans_Will_Be_Addressed_Prior_to_…
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: JPN-87-035, Forwards Insp Summary of Igscc,Per Util 861028 Commitment. Welds Classified According to NUREG-0313,Rev 2.Specific Insp Plans Will Be Addressed Prior to Next Scheduled Refueling Outage.Two Oversize Drawings Encl

LER-1986-028, :on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced
type: Subject
label: 05000322/LER-1986-028, :on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced
page: https://kanterella.com/05000322/LER-2D1986-2D028-2C_-3Aon_860710-2Cenvironmentally_Unqualified_Jumper_Wires_Installed_in_Valve_Operators_Contrary_to_License_Condition.Caused_by_Inability_to_Provide_Do…
wiki namespace: 0
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system: Reactor Water Recirculation
wiki page sort key: 05000322/LER-1986-028, :on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced

LER-1986-030, :on 860802,main Turbine & Reactor Feedwater Pumps Tripped Due to Feedwater Flow Oscillations.Caused by Opening of Min Flow Bypass Valves Due to Setpoint Error. Procedure Revised & Instruments Calibr
type: Subject
label: 05000321/LER-1986-030, :on 860802,main Turbine & Reactor Feedwater Pumps Tripped Due to Feedwater Flow Oscillations.Caused by Opening of Min Flow Bypass Valves Due to Setpoint Error. Procedure Revised & Instruments Calibr
page: https://kanterella.com/05000321/LER-2D1986-2D030-2C_-3Aon_860802-2Cmain_Turbine_-26_Reactor_Feedwater_Pumps_Tripped_Due_to_Feedwater_Flow_Oscillations.Caused_by_Opening_of_Min_Flow_Bypass_Valves_Due_t…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000321/LER-1986-030, :on 860802,main Turbine & Reactor Feedwater Pumps Tripped Due to Feedwater Flow Oscillations.Caused by Opening of Min Flow Bypass Valves Due to Setpoint Error. Procedure Revised & Instruments Calibr

LER-1986-011, :on 860520,full Reactor Scram Occurred Due to Low Reactor Water Level.Caused by Personnel Error.Procedural Violation Rept Completed & Reactor Operator Informed of Necessity of Proper RWCU Sys Isolation
type: Subject
label: 05000237/LER-1986-011, :on 860520,full Reactor Scram Occurred Due to Low Reactor Water Level.Caused by Personnel Error.Procedural Violation Rept Completed & Reactor Operator Informed of Necessity of Proper RWCU Sys Isolation
page: https://kanterella.com/05000237/LER-2D1986-2D011-2C_-3Aon_860520-2Cfull_Reactor_Scram_Occurred_Due_to_Low_Reactor_Water_Level.Caused_by_Personnel_Error.Procedural_Violation_Rept_Completed_-26_Reactor_…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000237/LER-1986-011, :on 860520,full Reactor Scram Occurred Due to Low Reactor Water Level.Caused by Personnel Error.Procedural Violation Rept Completed & Reactor Operator Informed of Necessity of Proper RWCU Sys Isolation

05000271/LER-1997-023, :on 971125,plant Trip Occurred.Caused by Failure of Protective Device in Main Generator Protective Circuitry.Operating Staff Placed Plant in Normal Shutdown Configuration
type: Subject
page: https://kanterella.com/05000271/LER-2D1997-2D023-2C_-3Aon_971125-2Cplant_Trip_Occurred.Caused_by_Failure_of_Protective_Device_in_Main_Generator_Protective_Circuitry.Operating_Staff_Placed_Plant_in_Nor…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000271/LER-1997-023, :on 971125,plant Trip Occurred.Caused by Failure of Protective Device in Main Generator Protective Circuitry.Operating Staff Placed Plant in Normal Shutdown Configuration

LER-1998-012, :on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With
type: Subject
label: 05000333/LER-1998-012, :on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With
page: https://kanterella.com/05000333/LER-2D1998-2D012-2C_-3Aon_981104-2Cfailure_to_Meet_Primary_Containment_Leakage_Rate_Testing_Program_Requirements_Was_Noted.Caused_by_Deficient_Test_Procedures.Leak_Rate…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1998-012, :on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With

LER-1998-008, :on 980803,automatic Reactor Scram Occurred Due to Low RPV Water Level Following Degradation in Feedwater Flow.Completed Post Transient Evaluation Prior to Startup & Correcting Filling & Venting Procedure
type: Subject
label: 05000333/LER-1998-008, :on 980803,automatic Reactor Scram Occurred Due to Low RPV Water Level Following Degradation in Feedwater Flow.Completed Post Transient Evaluation Prior to Startup & Correcting Filling & Venting Procedure
page: https://kanterella.com/05000333/LER-2D1998-2D008-2C_-3Aon_980803-2Cautomatic_Reactor_Scram_Occurred_Due_to_Low_RPV_Water_Level_Following_Degradation_in_Feedwater_Flow.Completed_Post_Transient_Evaluati…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1998-008, :on 980803,automatic Reactor Scram Occurred Due to Low RPV Water Level Following Degradation in Feedwater Flow.Completed Post Transient Evaluation Prior to Startup & Correcting Filling & Venting Procedure

05000333/LER-1992-053, :on 921228,Group I Isolations Occurred While Performing Surveillance Testing in Support of Unit Startup. Caused by Failed Relay.Relay Replaced & Satisfactory Testing Completed
type: Subject
page: https://kanterella.com/05000333/LER-2D1992-2D053-2C_-3Aon_921228-2CGroup_I_Isolations_Occurred_While_Performing_Surveillance_Testing_in_Support_of_Unit_Startup._Caused_by_Failed_Relay.Relay_Replaced_-…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1992-053, :on 921228,Group I Isolations Occurred While Performing Surveillance Testing in Support of Unit Startup. Caused by Failed Relay.Relay Replaced & Satisfactory Testing Completed

LER-1992-013, :on 920226,determined That Actual Design & Design Described in FSAR Differ for Air Conditioning Sys for Environ Encls.Caused by Incomplete Understanding of Design & Operation of Equipment.Load Ctrs Qualified
type: Subject
label: 05000333/LER-1992-013, :on 920226,determined That Actual Design & Design Described in FSAR Differ for Air Conditioning Sys for Environ Encls.Caused by Incomplete Understanding of Design & Operation of Equipment.Load Ctrs Qualified
page: https://kanterella.com/05000333/LER-2D1992-2D013-2C_-3Aon_920226-2Cdetermined_That_Actual_Design_-26_Design_Described_in_FSAR_Differ_for_Air_Conditioning_Sys_for_Environ_Encls.Caused_by_Incomplete_Und…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1992-013, :on 920226,determined That Actual Design & Design Described in FSAR Differ for Air Conditioning Sys for Environ Encls.Caused by Incomplete Understanding of Design & Operation of Equipment.Load Ctrs Qualified

LER-1992-047, :on 921104,automatic Shutdown Cooling Occurred Due to Loss of Power to Rps.Caused by Voltage Drop When Starting Large Electrical Load.Protective Device Setpoint Will Be Evaluated
type: Subject
label: 05000333/LER-1992-047, :on 921104,automatic Shutdown Cooling Occurred Due to Loss of Power to Rps.Caused by Voltage Drop When Starting Large Electrical Load.Protective Device Setpoint Will Be Evaluated
page: https://kanterella.com/05000333/LER-2D1992-2D047-2C_-3Aon_921104-2Cautomatic_Shutdown_Cooling_Occurred_Due_to_Loss_of_Power_to_Rps.Caused_by_Voltage_Drop_When_Starting_Large_Electrical_Load.Protective…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1992-047, :on 921104,automatic Shutdown Cooling Occurred Due to Loss of Power to Rps.Caused by Voltage Drop When Starting Large Electrical Load.Protective Device Setpoint Will Be Evaluated

2 Inch Equalization Line Plant Mod M1-92-383
type: Subject
label: JPN-92-067, Forwards Root Cause Failure Analysis of Equalization Line on Reactor Water Cleanup Valve 12RWC-46, & ASME Section XI Repair Program for Repair of RWCU Valve 12RWC-46 - 1/2 Inch Equalization Line Plant Mod M1-92-383
page: https://kanterella.com/JPN-2D92-2D067-2C_Forwards_Root_Cause_Failure_Analysis_of_Equalization_Line_on_Reactor_Water_Cleanup_Valve_12RWC-2D46-2C_-26_ASME_Section_XI_Repair_Program_for_Repair_of_RWCU_Va…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: JPN-92-067, Forwards Root Cause Failure Analysis of Equalization Line on Reactor Water Cleanup Valve 12RWC-46, & ASME Section XI Repair Program for Repair of RWCU Valve 12RWC-46 - 1/2 Inch Equalization Line Plant Mod M1-92-383

LER-1995-015-01, :on 951215,discovered Omission of RWR Seal Purge Flow from Reactor Heat Balance.Caused by Inadequacy in Original Plant Design.Restricted Plant Output to 2434 Mwt to Maintain More than 1.4 Mwt Margin
type: Subject
label: 05000333/LER-1995-015-01, :on 951215,discovered Omission of RWR Seal Purge Flow from Reactor Heat Balance.Caused by Inadequacy in Original Plant Design.Restricted Plant Output to 2434 Mwt to Maintain More than 1.4 Mwt Margin
page: https://kanterella.com/05000333/LER-2D1995-2D015-2D01-2C_-3Aon_951215-2Cdiscovered_Omission_of_RWR_Seal_Purge_Flow_from_Reactor_Heat_Balance.Caused_by_Inadequacy_in_Original_Plant_Design.Restricted_Pl…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1995-015-01, :on 951215,discovered Omission of RWR Seal Purge Flow from Reactor Heat Balance.Caused by Inadequacy in Original Plant Design.Restricted Plant Output to 2434 Mwt to Maintain More than 1.4 Mwt Margin

05000333/LER-1995-013-01, :on 950905,discovered Loss Feedwater Flow Transient Due to Personnel Error.Revised Abnormal Operating Procedure AOP-1
type: Subject
page: https://kanterella.com/05000333/LER-2D1995-2D013-2D01-2C_-3Aon_950905-2Cdiscovered_Loss_Feedwater_Flow_Transient_Due_to_Personnel_Error.Revised_Abnormal_Operating_Procedure_AOP-2D1
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1995-013-01, :on 950905,discovered Loss Feedwater Flow Transient Due to Personnel Error.Revised Abnormal Operating Procedure AOP-1

05000333/LER-1992-001-01, :on 920103,fire Watches Missed,Per Tech Spec 3.12.F.Caused by Inadequate Training & Supervision of Temporary Personnel.Supervisors Hired to Provide Training & Supervision
type: Subject
page: https://kanterella.com/05000333/LER-2D1992-2D001-2D01-2C_-3Aon_920103-2Cfire_Watches_Missed-2CPer_Tech_Spec_3.12.F.Caused_by_Inadequate_Training_-26_Supervision_of_Temporary_Personnel.Supervisors_Hire…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1992-001-01, :on 920103,fire Watches Missed,Per Tech Spec 3.12.F.Caused by Inadequate Training & Supervision of Temporary Personnel.Supervisors Hired to Provide Training & Supervision

ML20118D227
type: Subject
page: https://kanterella.com/ML20118D227
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20118D227

LER-1995-003, :on 950114,primary Containment Isolation Sys Group 2 Isolation Occurred.Caused by Abnormal Electrical Lineup & Procedural Deficiency.Procedure Controlling Bus Outage Restoration Will Be Revised
type: Subject
label: 05000333/LER-1995-003, :on 950114,primary Containment Isolation Sys Group 2 Isolation Occurred.Caused by Abnormal Electrical Lineup & Procedural Deficiency.Procedure Controlling Bus Outage Restoration Will Be Revised
page: https://kanterella.com/05000333/LER-2D1995-2D003-2C_-3Aon_950114-2Cprimary_Containment_Isolation_Sys_Group_2_Isolation_Occurred.Caused_by_Abnormal_Electrical_Lineup_-26_Procedural_Deficiency.Procedure…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1995-003, :on 950114,primary Containment Isolation Sys Group 2 Isolation Occurred.Caused by Abnormal Electrical Lineup & Procedural Deficiency.Procedure Controlling Bus Outage Restoration Will Be Revised

ML20079N735
type: Subject
page: https://kanterella.com/ML20079N735
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20079N735

LER-1990-020, :on 900626,shutdown Cooling Mode of RHR Sys Isolated.Caused by Air in Pressure Switch Sensing Line Due to Deficient Installation Design.Possible Design Mod to Sensing Line to Eliminate Air Trap Considered
type: Subject
label: 05000333/LER-1990-020, :on 900626,shutdown Cooling Mode of RHR Sys Isolated.Caused by Air in Pressure Switch Sensing Line Due to Deficient Installation Design.Possible Design Mod to Sensing Line to Eliminate Air Trap Considered
page: https://kanterella.com/05000333/LER-2D1990-2D020-2C_-3Aon_900626-2Cshutdown_Cooling_Mode_of_RHR_Sys_Isolated.Caused_by_Air_in_Pressure_Switch_Sensing_Line_Due_to_Deficient_Installation_Design.Possible…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1990-020, :on 900626,shutdown Cooling Mode of RHR Sys Isolated.Caused by Air in Pressure Switch Sensing Line Due to Deficient Installation Design.Possible Design Mod to Sensing Line to Eliminate Air Trap Considered

03L-0:on 820616,recirculation Flow Transmitter 02-FT-110D Found Out of Calibr Causing Small Error in Half of Average Power Range Monitor Setpoint.Caused by Instrument Drift.Instrument Recalibr
type: Subject
label: 05000333/LER-1982-027-03, /03L-0:on 820616,recirculation Flow Transmitter 02-FT-110D Found Out of Calibr Causing Small Error in Half of Average Power Range Monitor Setpoint.Caused by Instrument Drift.Instrument Recalibr
page: https://kanterella.com/05000333/LER-2D1982-2D027-2D03-2C_/03L-2D0-3Aon_820616-2Crecirculation_Flow_Transmitter_02-2DFT-2D110D_Found_Out_of_Calibr_Causing_Small_Error_in_Half_of_Average_Power_Range_Mon…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1982-027-03, /03L-0:on 820616,recirculation Flow Transmitter 02-FT-110D Found Out of Calibr Causing Small Error in Half of Average Power Range Monitor Setpoint.Caused by Instrument Drift.Instrument Recalibr

ML20054A954
type: Subject
page: https://kanterella.com/ML20054A954
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20054A954

ML20062E793
type: Subject
page: https://kanterella.com/ML20062E793
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20062E793

IR 05000333/1993010
type: Subject
page: https://kanterella.com/IR_05000333/1993010
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000333/1993010

IR 05000333/1993012
type: Subject
page: https://kanterella.com/IR_05000333/1993012
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000333/1993012

IR 05000458/1993013
type: Subject
page: https://kanterella.com/IR_05000458/1993013
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000458/1993013

LER-1990-016, :on 900424,automatic Isolation Signal Closed Suction Valves from Reactor Water Recirculation Sys.On 900425,suction Valves Closed & RHR Pump Tripped.Caused by Chattering Pressure Switch.Switches Replaced
type: Subject
label: 05000333/LER-1990-016, :on 900424,automatic Isolation Signal Closed Suction Valves from Reactor Water Recirculation Sys.On 900425,suction Valves Closed & RHR Pump Tripped.Caused by Chattering Pressure Switch.Switches Replaced
page: https://kanterella.com/05000333/LER-2D1990-2D016-2C_-3Aon_900424-2Cautomatic_Isolation_Signal_Closed_Suction_Valves_from_Reactor_Water_Recirculation_Sys.On_900425-2Csuction_Valves_Closed_-26_RHR_Pump_…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1990-016, :on 900424,automatic Isolation Signal Closed Suction Valves from Reactor Water Recirculation Sys.On 900425,suction Valves Closed & RHR Pump Tripped.Caused by Chattering Pressure Switch.Switches Replaced

JAFP-93-0207, Monthly Operating Rept for Mar 1993 for Ja Fitzpatrick Nuclear Power Plant
type: Subject
page: https://kanterella.com/JAFP-2D93-2D0207-2C_Monthly_Operating_Rept_for_Mar_1993_for_Ja_Fitzpatrick_Nuclear_Power_Plant
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: JAFP-93-0207, Monthly Operating Rept for Mar 1993 for Ja Fitzpatrick Nuclear Power Plant

IR 05000333/1992027
type: Subject
page: https://kanterella.com/IR_05000333/1992027
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000333/1992027

LER-1990-011, :on 900320,reactor High Pressure Logic Tripped, Isolating RHR Shutdown Cooling Sys B & Causing Trip of Isolation Pressure Switches.Caused by Internal Flow Transmitted in Reverse Direction
type: Subject
label: 05000333/LER-1990-011, :on 900320,reactor High Pressure Logic Tripped, Isolating RHR Shutdown Cooling Sys B & Causing Trip of Isolation Pressure Switches.Caused by Internal Flow Transmitted in Reverse Direction
page: https://kanterella.com/05000333/LER-2D1990-2D011-2C_-3Aon_900320-2Creactor_High_Pressure_Logic_Tripped-2C_Isolating_RHR_Shutdown_Cooling_Sys_B_-26_Causing_Trip_of_Isolation_Pressure_Switches.Caused_by…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1990-011, :on 900320,reactor High Pressure Logic Tripped, Isolating RHR Shutdown Cooling Sys B & Causing Trip of Isolation Pressure Switches.Caused by Internal Flow Transmitted in Reverse Direction

ML20034B801
type: Subject
page: https://kanterella.com/ML20034B801
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20034B801

IR 05000322/1989091
type: Subject
page: https://kanterella.com/IR_05000322/1989091
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000322/1989091

LER-1989-020, :on 891105,reactor Scram Occurred Due to Failure in Electronic Control Card of electro-hydraulic Control Sys.Caused by Void Collapse in Core Moderator. Circuit Boards Sent to Vendor for Analysis
type: Subject
label: 05000333/LER-1989-020, :on 891105,reactor Scram Occurred Due to Failure in Electronic Control Card of electro-hydraulic Control Sys.Caused by Void Collapse in Core Moderator. Circuit Boards Sent to Vendor for Analysis
page: https://kanterella.com/05000333/LER-2D1989-2D020-2C_-3Aon_891105-2Creactor_Scram_Occurred_Due_to_Failure_in_Electronic_Control_Card_of_electro-2Dhydraulic_Control_Sys.Caused_by_Void_Collapse_in_Core_M…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-1989-020, :on 891105,reactor Scram Occurred Due to Failure in Electronic Control Card of electro-hydraulic Control Sys.Caused by Void Collapse in Core Moderator. Circuit Boards Sent to Vendor for Analysis

ML20070V245
type: Subject
page: https://kanterella.com/ML20070V245
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20070V245

ML20031A465
type: Subject
page: https://kanterella.com/ML20031A465
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20031A465

ML20112D153
type: Subject
page: https://kanterella.com/ML20112D153
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20112D153

JAFP-89-0820, Annual Summary of Changes,Tests & Experiments Completed at James a Fitzpatrick Nuclear Power Plant During 1988
type: Subject
page: https://kanterella.com/JAFP-2D89-2D0820-2C_Annual_Summary_of_Changes-2CTests_-26_Experiments_Completed_at_James_a_Fitzpatrick_Nuclear_Power_Plant_During_1988
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: JAFP-89-0820, Annual Summary of Changes,Tests & Experiments Completed at James a Fitzpatrick Nuclear Power Plant During 1988

ML20126A126
type: Subject
page: https://kanterella.com/ML20126A126
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20126A126

ML20040F664
type: Subject
page: https://kanterella.com/ML20040F664
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML20040F664

ML19319A934
type: Subject
page: https://kanterella.com/ML19319A934
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML19319A934

JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions
type: Subject
page: https://kanterella.com/JAFP-2D24-2D0053-2C_License_Amendment_Request_to_Eliminate_Remaining_Main_Steam_Line_Radiation_Monitor_Initiated_Isolation_Functions
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: JAFP-24-0053, License Amendment Request to Eliminate Remaining Main Steam Line Radiation Monitor Initiated Isolation Functions

ML22325A126
type: Subject
page: https://kanterella.com/ML22325A126
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML22325A126

ML22292A091
type: Subject
page: https://kanterella.com/ML22292A091
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML22292A091

JAFP-23-0064, Emergency Plan Document Revision
type: Subject
page: https://kanterella.com/JAFP-2D23-2D0064-2C_Emergency_Plan_Document_Revision
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: JAFP-23-0064, Emergency Plan Document Revision

ML23062A420
type: Subject
page: https://kanterella.com/ML23062A420
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML23062A420

IR 05000259/2019002
type: Subject
page: https://kanterella.com/IR_05000259/2019002
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000259/2019002

ML19114A153
type: Subject
page: https://kanterella.com/ML19114A153
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML19114A153

ML18039A852
type: Subject
page: https://kanterella.com/ML18039A852
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML18039A852

IR 05000259/1996008
type: Subject
page: https://kanterella.com/IR_05000259/1996008
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000259/1996008

IR 05000259/1995059
type: Subject
page: https://kanterella.com/IR_05000259/1995059
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000259/1995059

LER-1994-011, Forwards Voluntary LER 94-011 Re Failure of Magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Valve.Rept Submitted Because of Potential Generic Applicability of Issues Surrounding Event to Other Util
type: Subject
label: 05000260/LER-1994-011, Forwards Voluntary LER 94-011 Re Failure of Magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Valve.Rept Submitted Because of Potential Generic Applicability of Issues Surrounding Event to Other Util
page: https://kanterella.com/05000260/LER-2D1994-2D011-2C_Forwards_Voluntary_LER_94-2D011_Re_Failure_of_Magnesium_Alloy_Rotor_Motor_on_Reactor_Water_Recirculation_Sys_Pump_Discharge_Valve.Rept_Submitted_Bec…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000260/LER-1994-011, Forwards Voluntary LER 94-011 Re Failure of Magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Valve.Rept Submitted Because of Potential Generic Applicability of Issues Surrounding Event to Other Util

ML18038B592
type: Subject
page: https://kanterella.com/ML18038B592
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML18038B592

LER-1994-011-01, :on 941001,magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Isolation Valve Failed,Placing Facility in Lco.New Operator Motor Installed & Associated Breaker Replaced
type: Subject
label: 05000260/LER-1994-011-01, :on 941001,magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Isolation Valve Failed,Placing Facility in Lco.New Operator Motor Installed & Associated Breaker Replaced
page: https://kanterella.com/05000260/LER-2D1994-2D011-2D01-2C_-3Aon_941001-2Cmagnesium_Alloy_Rotor_Motor_on_Reactor_Water_Recirculation_Sys_Pump_Discharge_Isolation_Valve_Failed-2CPlacing_Facility_in_Lco.N…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000260/LER-1994-011-01, :on 941001,magnesium Alloy Rotor Motor on Reactor Water Recirculation Sys Pump Discharge Isolation Valve Failed,Placing Facility in Lco.New Operator Motor Installed & Associated Breaker Replaced

IR 05000259/1990037
type: Subject
page: https://kanterella.com/IR_05000259/1990037
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000259/1990037

IR 05000259/1992030
type: Subject
page: https://kanterella.com/IR_05000259/1992030
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000259/1992030

ML18024A977
type: Subject
page: https://kanterella.com/ML18024A977
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML18024A977

ML17305A215
type: Subject
page: https://kanterella.com/ML17305A215
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML17305A215

IR 05000397/1989015
type: Subject
page: https://kanterella.com/IR_05000397/1989015
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000397/1989015

IR 05000397/1996007
type: Subject
page: https://kanterella.com/IR_05000397/1996007
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000397/1996007

JAFP-17-0054, Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay
type: Subject
page: https://kanterella.com/JAFP-2D17-2D0054-2C_Submittal_of_Stress_Analysis_Summary_for_the_24-2D10-2D130_Weld_Overlay
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: JAFP-17-0054, Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay

ML17219A123
type: Subject
page: https://kanterella.com/ML17219A123
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML17219A123

IR 05000259/1995047
type: Subject
page: https://kanterella.com/IR_05000259/1995047
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000259/1995047

ML17130A249
type: Subject
page: https://kanterella.com/ML17130A249
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML17130A249

ML17174A896
type: Subject
page: https://kanterella.com/ML17174A896
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML17174A896

05000333/LER-2017-002, Regarding Residual Heat Removal to Reactor Water Recirculation Loop a Weld Flaw Indication
type: Subject
page: https://kanterella.com/05000333/LER-2D2017-2D002-2C_Regarding_Residual_Heat_Removal_to_Reactor_Water_Recirculation_Loop_a_Weld_Flaw_Indication
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-2017-002, Regarding Residual Heat Removal to Reactor Water Recirculation Loop a Weld Flaw Indication

IR 05000333/2016004
type: Subject
page: https://kanterella.com/IR_05000333/2016004
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: IR 05000333/2016004

ML18023A468
type: Subject
page: https://kanterella.com/ML18023A468
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML18023A468

05000333/LER-2016-001, Regarding System Actuations During Manual Scram in Response to Frazil Ice Blockage and Residual Transfer
type: Subject
page: https://kanterella.com/05000333/LER-2D2016-2D001-2C_Regarding_System_Actuations_During_Manual_Scram_in_Response_to_Frazil_Ice_Blockage_and_Residual_Transfer
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-2016-001, Regarding System Actuations During Manual Scram in Response to Frazil Ice Blockage and Residual Transfer

ML14318A458
type: Subject
page: https://kanterella.com/ML14318A458
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML14318A458

ML112580401
type: Subject
page: https://kanterella.com/ML112580401
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML112580401

RS-11-123, Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for Rcs
type: Subject
page: https://kanterella.com/RS-2D11-2D123-2C_Supplemental_Information_Related_to_License_Amendment_Request_for_Adoption_of_Technical_Specifications_Task_Force_-28TSTF-29_Traveler_TSTF-2D514-2C_Revision_3-2…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: RS-11-123, Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for Rcs

RS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation
type: Subject
page: https://kanterella.com/RS-2D11-2D036-2C_License_Amendment_Request_for_Adoption_of_Technical_Specifications_Task_Force_-28TSTF-29_Traveler_TSTF-2D514-2C_Revision_3-2C_Revise_BWR_Operability_Requirement…
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: RS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation

05000333/LER-2005-004, Re Residual Heat Removal (RHR) Shutdown Cooling Line Through-Wall Crack
type: Subject
page: https://kanterella.com/05000333/LER-2D2005-2D004-2C_Re_Residual_Heat_Removal_-28RHR-29_Shutdown_Cooling_Line_Through-2DWall_Crack
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: 05000333/LER-2005-004, Re Residual Heat Removal (RHR) Shutdown Cooling Line Through-Wall Crack

ML100430356
type: Subject
page: https://kanterella.com/ML100430356
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML100430356

ML050320208
type: Subject
page: https://kanterella.com/ML050320208
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML050320208

ML051180046
type: Subject
page: https://kanterella.com/ML051180046
wiki namespace: 0
wiki page content language: en
system: Reactor Water Recirculation
wiki page sort key: ML051180046

ML050770041
type: Subject
page: https://kanterella.com/ML050770041
wiki namespace: 0
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RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation
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ML20126G581
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ML14261A309
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ML20112D272
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CNL-22-009, Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In.
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NUREG-1307, Rev. 20, Report on Waste Burial Charges: Changes in Decommissioning Waste Disposal Costs at Low-Level Waste Burial Facilities Final Report
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JAFP-19-0083, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation
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IR 05000333/2024004
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ML20236M919
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PY-CEI-NRR-0716, Informs That Testing & Review of Updated Inservice Testing Program for Pumps & Valves Identified Need for New Relief Requests.Listing of New & Revised Relief Requests Encl.Fee Paid
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LER-1995-011-01, :on 950531,leakage of Primary Containment Isolation Valves Was Exceeded.Caused by 02-2AOV-39 & 02- 2AOV-40 Experiencing Repeated Difficulty in Passing Llrt. Flushed Seat on Inboard Isolation Valve
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05000333/LER-1995-010-01, :on 950530,TS Required Plant Shutdown Due to Unidentified Leakage Into Drywell.Repacked Valve 02-RWR-52B Using Current Maint Practice of Repacking w/non-asbestos Graphite
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LER-1991-006-01, :on 910507,manual Reactor Shutdown Occurred Due to Inoperability of Both Low Pressure Coolant Injection Subsystems.Caused Mechancial Failure of One Valve in Each of Two Sys.Root Cause Investigation Started
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Plant Procedures
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IR 05000333/2025002
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JAFP-25-0046, License Amendment Request - Proposed Change to the Technical Specifications to Revise the Allowable Value for Reactor Water Cleanup (RWCU) System Primary Containment Isolation
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