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
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 7
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Section 15.2
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 7.0 - Instrumentation and Controls
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 7.0 - Instrumentation and Controls
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
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
B18729, License Basis Document Change Request 3-5-02 Limiting Safety System Settings and Instrumentation
SBK-L-06227, Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis Document
BYRON 2007-0055, B2R13, Spring 2007 Outage, Inservice Inspection Summary Report, for Inspection Activities from October 12, 2005 to May 3, 2007, Section 5.0 (Continued) Form NIS-2: Repairs/Modifications Through End
NOC-AE-07002104, Response to NRC Request for Additional Information on Proposed Change to Technical Specification 3.3.3.6, Accident Monitoring Instrumentation
L-2006-001, Proposed License Amendment Withdrawal Reactor Protection System Technical Specification Changes
L-2005-006, Proposed License Amendment Reactor Trip System Technical Specifications Changes
NOC-AE-040016, Broad-Scope Risk-Informed Technical Specification Amendment Request
DCL-03-016, License Amendment Request 03-02, Response Time Testing Elimination & Revision to TS 3.3.1, Reactor Trip System Instrumentation
BECO-90-139, Forwards Operability Evaluation in Response to NRC Bulletin 90-001 Re Loss of fill-oil in Transmitters Mfg by Rosemount
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
1CAN088907, Requests Relief from Impractical ASME Code Section XI Requirement to Perform 57 Exams of Partially Accessible Welds from First Inservice Insp Interval
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
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
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
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
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
ST-HL-AE-2636, Annual Environ Operating Rept for 1987
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
L-01-220, Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept
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
05000250/LER-2012-003, Regarding Condition Prohibited by Technical Specifications Due to Instrument Valve Mispositioning
RA-21-0191, License Amendment Request to Revise Technical Specifications Related to Reactor Protection System Instrumentation