P.7-28o-29
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CP-201201129, License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 7
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NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2
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WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls
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NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 7.0 - Instrumentation and Controls
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RS-12-221, Byron, Units 1 and 2, Updated Final Safety Analysis Report, Revision 14, Chapter 2.0 - Site Characteristics, Table of Contents Through Table 2.5-35
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RNP-RA/09-0054, Attachments VI & VII to Serial: RNP-RA/09-0054 - Request for Technical Specifications Change to Section 3.3.1 Reactor Protection System Instrumentation
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B18729, License Basis Document Change Request 3-5-02 Limiting Safety System Settings and Instrumentation
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SBK-L-06227, Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis Document
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Modifications Through End
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NOC-AE-07002104, Response to NRC Request for Additional Information on Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation
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L-2006-001, Proposed License Amendment Withdrawal Reactor Protection System Technical Specification Changes
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L-2005-006, Proposed License Amendment Reactor Trip System Technical Specifications Changes
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NOC-AE-040016, Broad-Scope Risk-Informed Technical Specification Amendment Request
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DCL-03-016, License Amendment Request 03-02, Response Time Testing Elimination & Revision to TS 3.3.1, Reactor Trip System Instrumentation
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BECO-90-139, Forwards Operability Evaluation in Response to NRC Bulletin 90-001 Re Loss of fill-oil in Transmitters Mfg by Rosemount
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PNO-V-86-045, on 860717,reactor Trip Occurred from 3- Power. Caused by Momentary Drop in Voltage Through break-before- Make Switch.Momentary Drop Allowed Permissive P7 to Unblock & Trip Signal Went to Reactor Protection Sys
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ML20235S495
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ML20216D822
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1CAN088907, Requests Relief from Impractical ASME Code Section XI Requirement to Perform 57 Exams of Partially Accessible Welds from First Inservice Insp Interval
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B12136, Forwards Revised Pages to Attachments 2 & 3 of Re 10CFR50,App J Exemption Request Concerning Testing of Containment Isolation Valve in Reverse Direction & Addition of Penetration Requiring Schedular Exemption
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Seven Oversize Tables
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label: B11874, Submits Corrections to Inconsistencies Noted in FSAR Section 7.2.1.1.2 Re Reactor Trips,Table 5.2-4 Re Reactor Coolant Water Chemistry Spec & Table 6.3-1 Re ECCS Component Parameters.W/Seven Oversize Tables
page: https://kanterella.com/B11874-2C_Submits_Corrections_to_Inconsistencies_Noted_in_FSAR_Section_7.2.1.1.2_Re_Reactor_Trips-2CTable_5.2-2D4_Re_Reactor_Coolant_Water_Chemistry_Spec_-26_Table_6.3-2D1_Re_EC…
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wiki page sort key: B11874, Submits Corrections to Inconsistencies Noted in FSAR Section 7.2.1.1.2 Re Reactor Trips,Table 5.2-4 Re Reactor Coolant Water Chemistry Spec & Table 6.3-1 Re ECCS Component Parameters.W/Seven Oversize Tables

ML22083A027
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ML22070A820
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ML20248E261
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ML20244D200
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ML20238F723
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ML20247K188
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Tech Specs
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label: 05000315/LER-1986-002, :on 860217,discovered That Three Reactor Trip Sys Interlock Setpoints Not Set Per Tech Spec Requirements. Caused by Misinterpretation of Tech Specs.Procedures Revised to Agree W/Tech Specs
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wiki page sort key: 05000315/LER-1986-002, :on 860217,discovered That Three Reactor Trip Sys Interlock Setpoints Not Set Per Tech Spec Requirements. Caused by Misinterpretation of Tech Specs.Procedures Revised to Agree W/Tech Specs

ML20207B671
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ML20199K846
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ML20198D832
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05000245/LER-1988-003-02, :on 880312,reactor Scram on Low Water Level Occurred.Caused by Feed Pump Trip.Feedwater Pump a Low Suction Pressure Switch Replaced,Recalibr & Tested Satisfactorily
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page: https://kanterella.com/05000245/LER-2D1988-2D003-2D02-2C_-3Aon_880312-2Creactor_Scram_on_Low_Water_Level_Occurred.Caused_by_Feed_Pump_Trip.Feedwater_Pump_a_Low_Suction_Pressure_Switch_Replaced-2CRecal…
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wiki page sort key: 05000245/LER-1988-003-02, :on 880312,reactor Scram on Low Water Level Occurred.Caused by Feed Pump Trip.Feedwater Pump a Low Suction Pressure Switch Replaced,Recalibr & Tested Satisfactorily

LER-1988-005, :on 880119,cold Overpressure Protection Sys Failed to Operate During Pressure Transient.Caused by Closure of RHR Valves Due to Misuse of Design Drawings. Procedure to Use Sys Being Prepared
type: Subject
label: 05000423/LER-1988-005, :on 880119,cold Overpressure Protection Sys Failed to Operate During Pressure Transient.Caused by Closure of RHR Valves Due to Misuse of Design Drawings. Procedure to Use Sys Being Prepared
page: https://kanterella.com/05000423/LER-2D1988-2D005-2C_-3Aon_880119-2Ccold_Overpressure_Protection_Sys_Failed_to_Operate_During_Pressure_Transient.Caused_by_Closure_of_RHR_Valves_Due_to_Misuse_of_Design_…
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ST-HL-AE-2636, Annual Environ Operating Rept for 1987
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LER-1988-007, :on 880203,manual Reactor Trip Initiated Due to Inoperable Digital Rpi.Caused by Equipment Failure.Display Card for Rod N-11 Warped Resulting in Pins on Card to Contact Adjacent Card.Display Card Replaced
type: Subject
label: 05000423/LER-1988-007, :on 880203,manual Reactor Trip Initiated Due to Inoperable Digital Rpi.Caused by Equipment Failure.Display Card for Rod N-11 Warped Resulting in Pins on Card to Contact Adjacent Card.Display Card Replaced
page: https://kanterella.com/05000423/LER-2D1988-2D007-2C_-3Aon_880203-2Cmanual_Reactor_Trip_Initiated_Due_to_Inoperable_Digital_Rpi.Caused_by_Equipment_Failure.Display_Card_for_Rod_N-2D11_Warped_Resulting_…
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L-01-220, Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept
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ML20081D161
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ML20070B367
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ML20128D818
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IR 015000004/1990006
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ML20070U682
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IR 05000282/1990004
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ML20008G244
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ML19347B963
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ML20035G140
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ML20059B548
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ML18152A408
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ML18017B725
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GO2-83-875, Discusses History & Background of Use of Fire Dampers Not Fire Rated or Tested in Const of Facility,Due to state-of- the-art Const at Time of Installation.Fsar Will Be Revised Via Amend 33 to Document const.Marked-up Drawings Encl
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IR 05000397/1978013
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ML13330B325
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05000250/LER-2012-003, Regarding Condition Prohibited by Technical Specifications Due to Instrument Valve Mispositioning
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ML12123A270
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ML13316B065
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ML18152A023
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ML052570650
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ML19308C282
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ML13311A734
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ML19247B184
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ML050200021
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ML20002B657
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ML20086A344
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ML20055G322
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ML20065T586
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ML18086A759
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ML22070A893
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ML21294A170
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ML21293A330
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IR 05000333/2001003
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IR 05000266/2003002
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RA-21-0191, License Amendment Request to Revise Technical Specifications Related to Reactor Protection System Instrumentation
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ML20309A756
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ML20217N719
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Cross cutting aspect
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