Low Pressure Cooling Injection# QUERYc6b85d30dd72fb2ef4cda49a405a9cf4
Low Pressure Cooling Injection
Low Pressure Cooling Injection# QUERYedb5a00598d32d15e19cd1305fd48e1e
Low Pressure Cooling Injection# QUERYabc7ad31dc5c164924d8816972ee821b
Low Pressure Cooling Injection# QUERYec966866b9333a851b430f8155be58f3
Low Pressure Cooling Injection# QUERY4fd1121340b437086869a72d4ffbb60a
NRC-11-0042, Day 10 CFR 50.46 Report - Plant Specific ECCS Evaluation Change
BVY 09-002, Supplemental Response to Generic Letter 2008-01
GO2-19-136, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to 10 CFR 50.54(F)Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-Ichi
PY-CEI-NRR-1849, Amends 940408 Response to GL 89-10,Suppl 6 to Include Info Obtained as Result of Refueling Outage 4 Activities.Gl 89-10 MOV Testing Schedule Extension & Application of Grouping Methodology,Bases & Justification Encl
05000324/LER-1989-004, :on 890225,steam Leak Occurred on RCIC Outboard Steam Supply Isolation Valve in Vicinity of Steam Leak Detection Temp Switch.Caused by Actuation of Steam Supply Isolation Valve.Weld Seal Completed
05000271/LER-1989-016, :on 890330,automatic Start of Core Spray & Sys a RHR Pumps Occurred While Pressurizing Primary Containment.Caused by Inadequate Procedure.Design Change That Implemented Logic Change Reviewed
05000324/LER-1989-004-02, :on 890225,channel a of RCIC Sys Steam Leak Detection Instrumentation Received Isolation Signal & Inboard Isolation Valve Isolated.Caused by Steam Leak.Valve Body to Bonnet Joint Wrapped W/Blankets
05000324/LER-1989-008-03, :on 890605,unplanned LOCA Initiation Signal Occurred During Routine Maint Testing of ECCS Resulting in Auto Starting of LPCI Core Spray & RHR Pumps.Caused by Spurious Trip of ECCS Trip Unit.Unit Replaced
05000374/LER-1989-004, :on 890201,determined That Static-O-Ring Min Flow Switch Exceeded Rejection Limits.Cause of Failure Could Not Be Determined from Insp.Replacement Flow Switch Installed,Calibr & Functionally Tested
05000277/LER-1987-023-01, :on 871014,HPCI Sys Disabled Due to Blown Logic Fuse.Cause Unknown.Fuse Replaced within 5 Minutes.No Addl Corrective Actions Planned
05000374/LER-1989-004-01, :on 890201,determined That Static O-Ring RHR Min Flow Switch Exceeded Rejection Limits During Instrument Surveillance.Reject & Flow Switches Replaced
05000277/LER-1987-022, :on 870929,HPCI Disabled Due to Blown Power Fuse in HPCI Logic Panel.Cause Unknown.Fuse Replaced within 35 Minutes,Static Inverter Placed on Ac Feed & Battery Terminal Voltage Monitored Every 4 H
05000341/LER-1987-009, :on 870325,RHR Pump C Tripped Due to Inboard Isolation Valve Closing.Caused by Intermittent Failure of Master Trip Unit.Futher Investigation of Master Trip Unit Will Be Made by Mfg.Isolation Logic Reset
05000325/LER-1988-020-01, :on 880915,RCIC Sys E51 Received Logic Channel B Supply Line Isolation,Closing Outboard Steam Supply Isolation Valve.Caused by Damage to Speed Sensor & Connector.Warning Signs Posted
05000325/LER-1985-059, :on 851102,reactor Scrammed Due to Primary Containment Group 1 Isolation,Rcic Trip & Trip/Lockout of Diesel Generator 4.Personnel Disciplined & Followup Meetings W/Shift Personnel Held
05000341/LER-1988-024, :on 880705,isolation of HPCI During Performance of Functional Test Occurred.Caused by Personnel Error. Surveillance Successfully Performed on Same Day & Accountability Meeting Held W/Individual
05000265/LER-1997-003-04, :on 970321,2B Core Spray Room Cooler Fouled Due to Hydrolyzing Debris.Cs Room Cooler Was Cleaned Under Nwr 960039336-01 & Qctp 1110-12, ECCS Room Cooler Trending Program, Has Recently Been Rewritten
05000296/LER-1985-006, :on 850213,mismatch Between Gemac Water Level Indicators Developed While at Low Pressure.Cause Attributed to Leak in Channel a Ref Leg Line X-28a.Operators Trained to Diagnose Water Level Problems
05000374/LER-1992-005-04, :on 920322, 2A DG Auto Started & RHR 2B Low Pressure Cooling Injection, 2C Low Pressure Cooling Injection & RCIC Sys Received Initiation Signals.Caused by Spike in Instrument Line.Procedure Revised
05000324/LER-1995-002-02, :on 950510,HPCI Sys Failed to Operate as Required During Performance of HPCI Periodic Test.Caused by End of Burnout.Verified Adequacy of Similar Resistors in Unit 1 & 2HPCI & RCIC Sys
BSEP-93-0033, Special Rept SR 2-93-0002:on 930209,reactor Bldg Fire Door 206 Declared Inoperable to Allow Equipment Cables & Lighting to Be Run Through Door.Compensatory Measures Remained in Effect Until Door Restored on 930223
BECO-90-041, Application for Amend to License DPR-35,changing Tech Spec 3/4.5, Core & Containment Cooling Sys to Reduce Unnecessary Wear Imposed by Excessive Surveillances on Operable Sys Components & Out of Svc Time to 72 H
05000325/LER-1989-023, :on 891116,reactor Shutdown When Drywell to Suppression Chamber Vacuum Breaker Opened.Caused by Excessive Vibration & Lack of Proper Space Between Actuator Arm & Piston.Procedures Will Be Revised
NRC-90-0025, Responds to NRC Re Violations Noted in Insp Rept 50-341/89-17.Corrective Actions:Design of Door Seal Air Supply Upgraded So That Single Failure Will Not Cause Loss of Door Integrity & Refresher Course Included in Training
05000325/LER-1989-021, :on 891022,inadvertent LOCA Initiation Signal Occurred During Monthly Channel Calibr & Functional Test. Caused by Technician Miscommunication.Involved Technicians Counseled
05000254/LER-1989-018-02, :on 891012,notification Given of Potential Single Failure of Diesel Generator Voltage Regulator That Could Result in Loss of All But One ECCS Loop.Caused by Design Deficiency.New Procedure Developed
05000324/LER-1989-008, :on 890605,unplanned LOCA Initiation Signal Occurred During Routine Maint Surveillance Testing of ECCS, Resulting in Autostarting of Core Spray a & B & RHR LPCI Pumps A,B,C & D.Caused by Spurious Trip
NRC-23-0063, Inservice Testing Program for Pumps and Valves - Part 12: IST Program Pump Basis Revision 1
05000260/LER-1996-005-01, :on 960510,unit Automatically Scrammed on Low Reactor Water Level Due to Runback of Reactor Feed Pumps. Caused by Inadequate Design of Digital Feedwater Control Sys Software.Design Change Implemented
NUREG-1433, Notice of Consideration of Issuance of Amend to License NPF-69 & Proposed NSHC Determination & Opportunity for Hearing.Amend Requests Full Conversion from Current TSs to Set of Improved TS Based on NUREG-1433 & NUREG-1434,rev 1
05000341/LER-1987-046, :on 870820,identified Deficiencies in Raychem Installations.Caused by Inadequacies in Training of Raychem Installers,Lack of Insp Requirement & Previous Specification Deficiencies.Installations Repaired & Replaced