Qualified Safety Parameter Display System
Qualified Safety Parameter Display System# QUERYc6b85d30dd72fb2ef4cda49a405a9cf4
Qualified Safety Parameter Display System# QUERY69ab641363df59814b05f2ec0cbddd62
Qualified Safety Parameter Display System# QUERY33d43075353219880f24be9b95d5e0ad
Qualified Safety Parameter Display System# QUERY25230d31cde1f76d60eb669a19e972c1
Qualified Safety Parameter Display System# QUERYe23e319f86729191842552b1bb0d9e32
05000362/LER-2009-001, Regarding Component Declared Inoperable After LCO Time Limit
W3F1-2013-0043, Request for Review and Approval of Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power
L-2013-141, Emergency Response Data System (ERDS) Changes Due to EPU
L-2013-084, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
L-2012-332, Emergency Response Data System (ERDS) Maintenance
L-2011-033, Emergency Response Data Point Library (Dpl) Changes/New ERDS Link
L-2010-255, Letter St. Lucie, Unit 2, Technical Specification Special Report Inoperable Reactor Water Level Monitoring System Channel Failed
L-2010-117, Technical Specification Special Report, Accident Monitoring Instrumentation Inoperable Channel a Reactor Vessel Level Monitoring System
L-2010-115, 10 CFR 50.59 Summary Report Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering May 11, 2008 Through December 4, 2009
L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08
L-2008-058, Emergency Response Data System Maintenance
LIC-07-0104, Revision to Technical Evaluation of Fort Calhoun Station, Unit No. 1, License Amendment Request, Modification of Surveillance Requirements for Emergency Mode (Remotely Operated) Dampers in Containment Air Cooling and Filtering System
L-2007-171, Emergency Response Data System (ERDS) Maintenance
L-2007-129, Emergency Response Data System (ERDS) Maintenance
W3F1-2006-0052, License Amendment Request NPF-38-267, Reactor Coolant System Leakage Detection Instrumentation, Waterford Steam Electric Station, Unit 3
W3F1-2006-0005, License Amendment Request NPF-38-267, Reactor Coolant System Leakage Detection Instrumentation
W3F1-2004-0004, Supplemental Information Extended Power Uprate - Power Ascension Testing
W3F1-2004-0052, Supplement to Amendment Request NPF-38-249, Extended Power Uprate
L-2003-292, Revised Emergency Plan Implementing Procedures
L-2003-242, 0 to EPIP-05, Activation and Operation of the Operational Support Center, and Revision 7 to EPIP-06, Activation and Operation of the Emergency Operations Facility
L-2003-052, Response to Request for Additional Information Regarding Relaxation Request for Us NRC Order EA-03-009
LIC-03-0015, Transmittal of Changes to Emergency Plan Implementing Procedure & Emergency Planning Forms
W3F1-2021-0001, Special Report SR-21-001-00 for Waterford Steam Electric Station, Unit 3 (Waterford 3) Re Reactor Vessel Level Monitoring System (Rvlms) Channel Inoperable for Greater than 30 Days
L-87-295, Forwards Rept of Brief Description of Plant Changes/Mods (Pcms) Made Under Provisions of 10CFR50.59,including Summary of Safety Evaluation for Each.Rept Includes PCMs Completed Between 860123-870122 & Correlates W/Rev 6 of Updated FSAR
L-97-089, Responds to Violations Noted in Insp Repts 50-335/97-01 & 50-389/97-01.Corrective Actions:Changed Equipment Clearance Order 1-97-01-093 & Associated Tags to Reflect Proper Description of Electrical Leads & Counseled Personnel
L-92-300, Forwards Data Point Library Revisions to Support Installation by NRC Onto Emergency Response Data Sys Computer
LIC-94-0110, Transmits Changes to Fort Calhoun Station Radiological Emergency Response Plan & Epips.W/O Encl
LIC-90-0632, Monthly Operating Rept for Jul 1990 for Fort Calhoun Station Unit 1
W3P87-1751, Rept of Facility Changes,Tests & Experiments for Mid-Yr 1987 Per 10CFR50.59
W3P88-1940, Responds to Item 2.2 (Part 2) of Generic Ltr 83-28 Re Program for Vendor Interface.Key Component List W/Manufacturer/Vendor Encl.Util Endorsed Nutac Document, Vendor Equipment Technical Info Program
W3P86-0048, Addendum 1 to Waterford Steam Electric Station Unit 3 Startup Rept
W3P83-3438, Forwards Response to SER Open Items 3 & 6 Re Inadequate Core Cooling (ICC) Instrumentation.Response Demonstrates That ICC Display Scheme Meets or Exceeds NUREG-0737,Item II.F.2 Requirements
W3P83-0847, Forwards Description of Inadequate Core Cooling Instrumentation,Including Evaluation of Compliance W/ Specific Requirements of NUREG-0737,Item II.F.2,per Ser. Info Will Be Incorporated in Amend 32 to FSAR
LD-83-049, Forwards Review of CESSAR-F Against Requirements of Cp/Ml Rule 10CFR50.34(f) & Selective Sections of App B & Chapter 3 of CESSAR-F.Only Fraction of Rule Requirements within Scope of CESSAR-F.CESSAR-F Complies W/Rule
W3P83-1542, Forwards Revised Description of NUREG-0737,Item II.F.2, Inadequate Core Cooling Instrumentation, Providing Sufficient Info to Close Item & Corresponding Requirement in SER
05000382/LER-1987-009, :on 870317,discovered That Instrument Used to Determine Containment Internal Pressure Not Sufficiently Accurate.Caused by Design Deficiency.Calculational Methodology Substituted
05000382/LER-1986-005, :on 860318,during Mode 5,Surveillance Procedure OP-903-013 Error Resulted in Hot Leg Temp Accident.Caused by Suspect Monitoring Instrument Operability.Procedure Changed
05000285/LER-1992-013, :on 920408,actuation of Engineered Safety Feature (ESF) Components Occurred.Caused by Spade Wire Lugs Loosening & Loss of Connection.Maint Procedure Requirements for Terminating Wires Revised
05000250/LER-1984-014, :on 840424,turbine Operator Taking Standby Static Inverter a Out of Svc Erroneously Opened Output Breaker of Adjacent Static Inverter,Causing Reactor Trip. Plant Stabilized & Instruments Replaced
05000362/LER-1983-108-03, /03L-0:on 831125,qualified Safety Parameter Display Sys (QSPDS) Channel a Failed & Declared Inoperable. Caused by Interference in Plasma Display Unit Due to Ground Loops.Grounding Configuration Modified
05000362/LER-1983-098-03, /03L-0:on 831108,qualified Safety Parameter Display Sys Channel a Observed Continuously Cycling Through Pages of Display & Channel Declared Inoperable.Caused by Loose Circuit Board.Loose Board Reseated
05000362/LER-1983-109-03, /03L-0:on 831111,qualified Safety Parameter Display Sys Channel a Began Intermittently Failing & Declared Inoperable.Caused by Failed Power Supply to Plasma Display.Power Supply Replaced
05000362/LER-1983-082-03, /03L-0:on 831005,qualified Safety Parameter Display Sys Train B Taken Out of Svc Due to Smoky Odor Eminating from Cabinet.Caused by Failed Circuit Board. Circuit Board Replaced
05000362/LER-1983-027-03, /03L-0:on 830307,train B RCS Subcooling Margin Monitor Failed to Meet Tech Spec Requirements & Declared Inoperable.Caused by Sys Ground on Qualified Safety Parameter Display Sys.Monitor Isolated
05000362/LER-1983-034-01, /01L-0:on 830527,potential for Loss of Indication During & After Seismic Event Discovered During Testing of Qualified Safety Parameter Display Sys Akin to Installed Sys.Caused by Loose Lockwasher
05000362/LER-1994-001-01, :on 940416,channel B Containment Emergency Sump Level Lumigraph Indicator 3LI-9389-2 Observed W/No Light Bars Illuminated.Caused by Failure of Level Signal Converter 3LY-9389-2.Failed Signal Converter Replaced
LIC-94-0093, Monthly Operating Rept for Apr 1994 for Fort Calhoun Station Unit 1
L-2022-142, Revised Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004
05000250/LER-1990-010, :on 900518,Mode 3 Entered W/O Having at Least One Channel of Reactor Vessel Level Monitoring Sys in Svc. Caused by Personnel Error.Heated Junction Thermocouple Breakers Closed & Procedures Revised
L-87-480, Forwards Summary of mgt-on-shift Repts Weekly Rept for Wk of 871109-16,per Commission 871019 Order
L-87-488, Forwards mgt-on-shift Weekly Rept for 871116-23,per NRC 871019 Order
L-87-495, Forwards Summary of Mgt on Shift Repts for Wk Starting 871123.Procedure O-ADM-019, Mgt on Shift Encl
L-91-287, Forwards Emergency Response Data Sys Implementation Plan & Description of Plant Computer Sys Configuration & Interface. Emergency Procedures Will Be Revised,As Necessary,To Ensure Activation of Sys within 1 H of Declaration of Alert
L-88-299, Forwards Summary of mgt-on-shift Repts for 880704-08,per NRC 871019 Order.Change Discussed & Concurred W/By Region II Staff
05000250/LER-1988-002, :on 880115,RCS Pressure Decreased to 625 Psig & Accumulators Started to Inject.Caused by Defective Controller for Valve PCV-3-455B.Controller Replaced
L-88-142, Forwards Summary of mgt-on-shift Weekly Repts,Per NRC 871019 Order
L-88-122, Forwards Summary of mgt-on-shift Weekly Rept for Wk Starting 880229,per NRC 871019 Order
05000528/LER-1998-008, :on 980729,EQ of Electrical Connectors Were Not Adequately Demonstrated.Caused Because Test Was Conducted with Only Single Lv Connector & Without Fully Ranged Inputs. Revised EQ Requirements
L-93-246, Rept of Changes Made to Facility Under Provisions of 10CFR50.59 for Period 911007-930325
L-83-133, Forwards Responses to Generic Ltr 82-28 Re Inadequate Core Cooling Sys for Facility.W/Five Oversize Drawings.Aperture Cards Are Available in PDR
L-83-209, Responds to Questions Raised During NRC 830223-24 Site Visit Re Availability of Readout of Core Exit Thermocouples When Plant Computer Down & Procedure for Loss of All Ac Power. Computer Readout Always Available Through Redundant Sys
L-83-332, Forwards List of Resolved License Conditions for Initial criticality.Post-fuel Load Initial Test Program Initiated, Including Criticality & Low Power Testing Described in Chapter 14 to FSAR
L-87-242, Forwards Addl Justification to Support Util Deviation from Reg Guide 1.97 Re Steam Generator wide-range Level Instrumentation.Instrumentation Beyond That Already Provided Not Considered Necessary for Safe Plant Operation
L-90-161, Forwards Final Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. One Untraceable Circuit Breaker Installed in Unit 2 Qualified SPDS & Replaced W/Traceable Breaker
05000382/LER-2011-004, Regarding Vendor Notification of Non-Conforming Part Renders Both Trains of QSPDS Inoperable
05000528/LER-2011-002, For Palo Verde, Unit 1, Regarding Nonconforming Condition Renders the Qualified Safety Parameter Display System Inoperable
05000250/LER-2007-004-01, Regarding Reactor Coolant System Boundary Leakage
05000250/LER-2007-004, Regarding Reactor Coolant System Boundary Leakage
05000251/LER-2003-001, From Turkey Point 4 Regarding Channel Failure of Qualified Safety Parameter Display System
L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004