Emergency Feedwater Initiation and Control
Emergency Feedwater Initiation and Control# QUERYc6b85d30dd72fb2ef4cda49a405a9cf4
Emergency Feedwater Initiation and Control# QUERY233d2aa027a3ddc62e04333a9f7fb3bc
Emergency Feedwater Initiation and Control# QUERY96b6252542192638b23f4672f88527e1
Emergency Feedwater Initiation and Control# QUERY42bd7ea84443f6ade89d2a7e4a1b19d9
Emergency Feedwater Initiation and Control# QUERYe2d28ed9a8ba6b5791055cfa72087040
05000302/LER-2013-001, Regarding Valid Actuation of an Emergency Diesel Generator Due to a Spurious Fault on a Breaker Non-Segregated Bus Duct
05000313/LER-2003-001, Unit 1 Reactor Trip Due to Automatic Actuation of the Reactor Protection System on High Reactor Coolant System Pressure and Actuation of the Emergency Feedwater System Resulting from a Lightning-Induced Closure
1CAN071701, License Amendment Request, Application for Technical Specification Improvement to Revise Actions for Inoperable Using the Consolidated Line Item Improvement Process
1CAN101701, License Amendment Request Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves
3F0516-05, Final Safety Analysis Report Revision 38 & May 2016 10 CFR 50.59 and 10 CFR 72.48 Report
0CAN011601, Notification of Full Compliance with NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Bdbees)
3F0515-05, Technical Specifications Bases Control Program
3F0514-08, NRC Commitment Change Report - May 2014
3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re
3F1012-06, CR-3 Extended Power Uprate LAR Supplement and Response to Third Request for Additional Information to Support NRC Instrumentation and Controls Branch (Eicb) Technical Review
0CAN081202, – Units 1 and 2: Response to Request for Additional Information Related to Proposed Emergency Action Levels Using NEI 99-01 Revision 5 Scheme
1CAN061201, License Amendment Request Technical Specification Change Associated with Main Feedwater Valves
3F0412-07, Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR
3F0312-02, Response to Second Request for Additional Information to Support NRC Instrumentation and Controls Branch (Eicb) Technical Review of the CR-3 Extended Power Uprate LAR
3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip
1CAN081001, License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves
TMI-10-021, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (Adoption of TSTF-425, Revision 3)
1CAN080801, Response to Request for Additional Information Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term
TSTF-08-10, Transmittal of TSTF-507, Revision 0, CLIIP Traveler to Increase Standardization
1CAN040802, Supplement to Amendment Request Regarding Technical Specification Changes and Analyses Relating to Use of Alternate Source Term
1CAN080601, License Amendment Request Regarding the Relocation of Inverter Y-28 and Panel C-540 Requirements from TSs to TRM
1CAN010606, Response to NRC Request Information Relating to Revision of Instrument Uncertainty Calculation Associated with the Emergency Feedwater Initiation and Control (EFIC) Steam Generator Level - Low Function
1CAN010605, Unit 1 Supplement to Amendment Request Response to Additional Questions Related to the Revision of the Allowable Value for Emergency Feedwater Initiation and Control Function (EFIC)
1CAN010603, Supplement to Amendment Request, Revision of the Allowable Value for Emergency Feedwater Initiation and Control Function (Efic), Enclosure 1, Calculation, Efic System Loop Error and Setpoint Analysis
1CAN010601, Supplement to Amendment Request, Revision of the Allowable Value for Emergency Feedwater Initiation and Control Function (EFIC)
3F0811-01, Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR
3F0711-07, Clarifications for Trace Confirmatory Model Development for Extended Power Uprate
3F0810-03, 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Small Break Loss of Coolant Accident Analysis
3F1209-04, Response to Follow-up to Progress Energy RAI Responses on CR-3 SAMA Evaluation
3F0505-07, Supplemental Information & Additional Commitment Regarding License Amendment Request No. 289, Revision 0, Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling System - Operating, 3.6.6, Reactor Building Spray
3F1203-03, License Amendment Request No. 281, Revision 0 Regarding Revised Improved Technical Specification (ITS) 3.7.5, Emergency Feedwater System
1CAN090401, Arkansas, Unit 1 - License Amendment Request Proposed Technical Specification Change for Revision to ANO-1 Steam Generator Tube Inservice Inspection Program
3F1203-15, Final Response to Request for Additional Information Related to Crystal River Unit 3 - Revised Appendix R Exemption Request - Fire Area CC-164-121
3F0703-04, License Amendment Request 280, Rev. 0 Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System
3F1103-07, Response to Request for Additional Information Related to Revised Appendix R Exemption Request, Fire Area CC-164-121
3F0502-06, Technical Specifications Bases Control Program
1CAN030201, License Amendment Request Re Proposed Change to Support Implementation of ANO-1 Improved Technical Specifications
05000302/LER-1983-023, Updated LER 83-023/01T-1:on 830613,fire Damper Discovered Missing.Approx 55 Addl Dampers & Chase Connecting Control Complex 108 & 165 Ft Elevations Degraded Due to Incorrect Fire Rating.Caused by Personnel Error
PNO-II-86-001, on 860101,reactor Tripped from High Flux to Flow Resulting in Actuation of Emergency Feedwater Initiation.Caused by Sheared Shaft on One of Four Reactor Coolant Pumps.Feedwater Flow Secured
1CAN069805, Documents Completion of Requested Actions of GL 96-01, Testing of Safety-Related Logic Circuits
3F0789-20, Responds to NRC Re Violations Noted in Insp Rept 50-302/89-09.Corrective Actions:Licensee Will Continue to Conduct High Energy Line Break Program to Resolve Deficiency & Long Term Equipment Qualification Program Developed
1CAN048914, Forwards Response to 890223 Request for Addl Info Re Facility ATWS Conceptual Design.Start Date for 1R9 Refueling Outage May Be Pushed from Spring,1990 to Late Summer-early Fall,1990 Due to 1R8 Outage Extension
1CAN048915, Application for Exigent Amend to License DPR-51,increasing Power to Analyzed Level of 80%.Fee Paid
3F0489-12, Forwards Response to Station Blackout Rule Implementation & Description of Severe Weather Procedures Which Will Be Implemented
NL-87-1584, Monthly Operating Rept for Nov 1987
1CAN128707, Forwards Info Re Elevated Reactor Bldg Temp & Schedule of Completion of All Committed Actions,Per NRC 871015 Request
NL-87-1411, Monthly Operating Rept for Oct 1987
3F1286-05, Forwards SAIC-86/1098, Crystal River Unit 3 Emergency Feedwater Sys Reliability Analysis. Study Incorporates All Recent Improvements to Sys.Sys Believed Highly Reliable & Adequate in Fulfilling Role in Accident Mitigation
3F0387-02, Forwards Info Re Generic Issue 124,auxiliary Feedwater Sys Reliability,Per NRC 870218 request.W/75 Oversize Drawings
1CAN128612, Responds to Notice of Violation & Imposition of Civil Penalty,Part Ii,From Insp Rept 50-313/86-01 During Jan 1986. Response to Part I Contained in .Reconsideration of Violation a Requested.Corrective Actions Discussed
3F0997-12, Confirms Completion of Requested Actions of GL 96-01 for Unit 3.Util Considers Requested Actions Completed
3F0486-15, Advises That Since Installation of Emergency Feedwater Initiation & Control Sys,Per NUREG-0737,Item II.E.1.2, Several Actuations Occurred.Temporary Fix of Installing Time Delay Relay Mfg by Logitek,Inc Underway
3F0199-01, Forwards Addl Info Re post-modification Testing of HPI & EFW Systems for Plant Changes Associated with Proposed LARs 240 & 241,dtd 981123 & 24.Some Details of Plans May Change as Specifics of Test Procedures Are Developed
3F0298-20, Forwards Suppl to Annual 10CFR50.59 Rept That Was Provided in .Attachment a Provides Descriptions of Changes to Facility as Described in FSAR That Were Implemented Between Dec 1996 & Nov 1997.No Tests or Experiments Done
1CAN058608, Responds to Open Items Noted in 860331 Safety Sys Functional Insp Rept 50-313/86-01 Re Emergency Feedwater Sys.Corrective Actions:Change Made to FSAR Sections to Expand & Upgrade Discussion of Postulated high-energy Line Breaks
3F1298-01, Forwards Response to NRC 980410 RAI Re Audit Rept of USI A-46,seismic Implementation & Subsequent Evaluations of Related Issues at Crystal River,Unit 3
0CAN108504, Forwards Response to 850807 Request for Addl Info to Complete Review of SPDS Per Suppl 1 to NUREG-0737
3F1297-47, Forwards Response to 971219 RAI Re TS Change Request Notice 210,addressing Design & Licensing Basis Changes Involving Plant Systems Used to Mitigate Consequences of Certain Sbloca.Commitments Made by Util Also Encl
3F0797-21, TS Change Request 209,Rev 1 for License DPR-72,adding EDG Kilowatt Indication to post-accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt
3F1198-01, Application for Amend to License DPR-72,consisting of LAR 240,re Addition of safety-related diesel-driven Emergency Feedwater Pump.Overview of Proposed Mods Presented to NRC on 980921.Addl Info on post-mod Testing Will Be Sent by 990129
3F1098-02, Application for Amend to License DPR-72,revising Improved Tech Specs (ITS) by Deleting Note Re Number of Required Channels for Degrees of Subcooling Function & Subdividing Core Exit Temp Into Two New Functions in ITS Table 3.3.17-1
3F0988-16, Forwards Results of Risk Assessment Associated W/High Energy Line Break Review Reported on 880907.Util Will Seek NRC Approval to Include Relief Granted in Generic Ltr 87-11 Re Elimination of Arbitrary Intermediate Pipe Breaks
3F0988-17, Forwards Review Summary Re Relationship Between Ser,B&W Owners Group Generic ATWS Design & Util Conceptual Design,As Requested in NRC .Rept MAR 84-06-07-01, ATWS Conceptual Design Also Encl
3F0888-06, Clarifies Justification for Continued Operation Re Environ Qualification of Feedwater Isolation Valves,Per Util & 880808 Telcon.Nonconforming Operations Rept Encl
3F0788-18, Forwards Status of Key Projects,Including Addl Feedwater Pump,Emergency Diesel Generator & UHS
NL-88-331, Monthly Operating Rept for Feb 1988
3F1296-09, Forwards 10CFR50.59(b)(2) Rept of Evaluations Which Have Resulted in No Unreviewed Safety Questions for Mods or Procedure Changes
3F0697-10, TS Change Request 210 to License DPR-72,supporting Operation W/Hardware Changes Primarily Involving Efw,Hpi,Emergency Feedwater Initiation & Control Sys & Edgs,As Well as Associated Licensing & Design Bases Changes
3F0697-12, Forwards Response to Violations Noted in Insp Rept 50-302/96-19.Corrective Actions:Mgt Conveyed Expectations for Effective 10CFR50.59 Evaluations to Those Individuals Involved W/Process
3F1085-14, Summarizes Programs & Improvements to Emergency Feedwater Sys for Facility.Sys Installed Which Can Automatically Start & Control Emergency Feedwater Sys & Prevent Overcooling
3F0497-34, Responds to NRC Re Violations Noted in Insp Repts 50-302/96-12 & 50-302/96-19.Corrective Actions:Mgt Conveyed Expectations for Effective 10CFR50.59 Evaluations & Established Safety Analysis Group to Perform Reviews
3F1196-07, Responds to NRC Re Violations Noted in Insp Rept 50-302/96-09.C/A:lead Technician for Task Counseled by Mgt on Inappropriateness of Decision to Allow Technician Who Was Not Qualified to Perform Work Independently
3F1096-22, Special Rept:On 960902,unit Shutdown Due to Leak in Turbine Lube Oil Sys.Issue Will Be Resolved Before Startup from Current Outage
CEO-88-113, Part 21 Rept Re Mfg Defect W/Gould Model PD3200 Pressure Transmitters.Three Failed Units Removed from Svc & Returned to Mfg for Analysis.Engineering Action Plan Formulated to Monitor Subj Transmitters & Replace Any Defective Devices
CEO-88-112, Forwards Preliminary Test Outline Re Emergency Feedwater Initiation & Control Sys Testing Scheduled for 80% Power Trip.Test Procedure Will Be Written & Forwarded by 880728
3F0996-05, Application for Amend to License DPR-72,consisting of Change Request 209,Rev 0,proposing Listed Changes to CR-3 post- Accident Monitoring Instrumentation TS
3F0585-14, Special Rept 85-02:on 850408,during Refueling & Mod Outage, Halon Portion of Fire Suppression Sys for Cable Spreading Room Taken Out of Svc in Support of Various Mods to Cable Spreading Room.Fire Watches Immediately Established
3F0685-29, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 122,Suppl 2,withdrawing Change to Item 6.a,Table 3.3-5,Page 3/4 3-17 Re ESF Response Times.B&W Reevaluating Main Feedwater Isolation Response Time
3F0996-01, Provides Response to Notice of Violation & Proposed Imposition of Civil Penalties Re Insp Rept 50-302/96-04. Corrective Actions:Restoring Adequate Operating Margins for make-up Tank Hydrogen Additions & Reducing Operator Burden
3F0185-08, Application for Amend to License DPR-72,changing Tech Specs to Provide Operability & Surveillance Requirements for Emergency Feedwater Sys Automatic & Manual Initiation Channels.Fee Paid
0CAN069602, Forwards Response to Violations Noted in Insp Repts 50-313/96-02 & 50-368/96-02.Corrective Actions:Valve Chain Reconfigured & Locked to Preclude Valve Operation
0CAN059601, Responds to NRC Ltr Re Violations Noted in Insp Repts 50-313/96-01 & 50-368/96-01 on 960121-0302.C/A:MDPI Units for HPSI Valves Removed & Reinstalled.Efic Heat Trace Controllers,Contactors & Alarm Relay Repaired
0CAN049603, Responds to GL 96-01, Testing of Safety-Related Logic Circuits
3F0385-03, Forwards Requests for Exemption from Required Schedule for Completion of Three Plant Fire Protection Mods,Superseding 841005 Requests.Completion Dates Extended to First Quarter 1986
3F0592-06, Responds to Notice of Violation & Forwards Payment of Civil Penalty in Amount of $50,000,per Insp Rept 50-302/91-25. Corrective Actions:Procedural Guidance Incorporated Into AI-50 Re Conduct of Operations.Final Rept Encl
3F1295-20, Provides Addl Info Re TS Change Request 202,suppl 2 Re 24 Month Fuel Cycle Surveillance Extensions
3F0492-10, Forwards Rev 2 to Pipe Rupture Analysis Criteria Outside Rb,Crystal River Unit 3. Greatest Potential for Postulated Terminal End Rupture Will Occur at 3-inch End of 6-inch by 3-inch Reducer
3F0884-07, Forwards Description of How Rev 3 to Reg Guide 1.97, Instrumentation for LWR Nuclear Power Plants to Assess Plant & Environs Condition During & Following Accident, Per Suppl 1 to NUREG-0737.Mods Will Be Implemented by 871231
3F1195-25, Submits Discussion in Response to Concerns Re Proposed TS Change Request to Extend Most Refueling Interval Surveillances to 24 Months.Revised Copies of Instrument Drift Studies Included in Original Submittal Attached Also
3F1195-14, Forwards Response to NRC Re Violations Noted in Insp Rept 50-302/95-16.Corrective Actions:Placed DC Cooling to MUP-1A Under Administrative Control
3F1095-21, Rescinds 1-h non-emergency Rept (NRC Event 29384) Re Two Valves,When Opened Simultaneously,Comprising Operation Outside Design Basis of Plant
1CAN078402, Requests Written Concurrence That 21,300 Gallons of Protected Water Sufficient to Allow Manual Switchover to Svc Water,Per NRC 840517 Request & NUREG-0737,Item II.E.1.1
3F0595-01, Application for Amend to License DPR-72,revising TSs to Allow Continuous Operation for Up to 24 Month Period
3F0391-15, Provides NRC W/Updated Design Info About Auxiliary Feedwater Pump Addition at Crystal River Unit 3 & Providing Revs to
1CAN948404, Notifies That Parallel Effort Underway for Design & Const of Condensate Storage Tank for Tornado Protection Per TMI Item 2.E.1.1.Written Concurrence Requested to Ensure Vol of Protected Water Sufficient to Resolve Concern GL-4
3F0495-08, Forwards Response to NRC Re Violations Noted in Insp Repts 50-302/94-22,50-302/94-25 & 50-302/95-02 & Proposed Imposition of Civil Penalty.C/A:Bypass Setpoints Adjusted
3F1183-03, Forwards Response to Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Event. Existing Program & Procedures Ensure High Degree of Reactor Trip Sys Reliability
L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3
3F0791-05, Provides Addl Info in Response to NRC Supplemental Safety Evaluation Re Station Blackout Rule Implementation for Crystal River Unit 3,per 910506 & s
3F0994-08, Application for Amend to License DPR-72,consisting of Tech Spec Change Request 199,Rev 0,increasing Rated Thermal Power Level
3F0894-02, Provides Response to NRC Request for Addl Info Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue,Per GL 87-02
1CAN119007, Provides Addl Info to Support Amend Request to Increase Reactor Power to 100%,per 901108 Request
1CAN119002, Forwards Responses to 901025 Request for Addl Info Re 100% Power Tech Spec Change
1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4
1CAN068202, Submits Addl Info Re Emergency Feedwater Sys Upgrade,Per NUREG-0737,Items II.E.1.1 & II.E.1.2.Equipment Scheduled for Installation During Refueling Outage Listed
3F0112-11, Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report
3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F1208-06, License Amendment Request 300, Revision 0 Addition of TSTF 479, Revision 0 and TSTF 497, Revision 0 to the Inservice Testing (IST) Program
3F0208-01, License Amendment Request 295, Revision 0: Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times - Response to Request for Additional Information
3F0506-03, License Amendment Request 264, Revision 0, Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity
3F0907-03, License Amendment Request 295, Revision 0: Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Response to Request for Additional Information
3F1206-02, License Amendment Request 264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information
3F0407-12, License Amendment Request 295, Revision 0, Extension of Allowed Outage Time to Seven Days and Elimination of Second Completion Times Limiting Time
3F0404-11, Modified Proposed License Condition, License Amendment Request 280, Revision 1, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System
3F0904-05, Supplemental Information and Regulatory Commitments for License Amendment Request 281, Revision 0, Revised Improved Technical Specification (ITS) 3.7.5, Emergency Feedwater System
3F0105-02, License Amendment Request 289, Revision 0 Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling Systems - Operating, 3.6.6, Reactor Building Spray & Containment Cooling Systems, 3.7.8, Decay Heat Closed Cycle.
3F0304-09, Proposed License Condition for License Amendment Request 280, Revision 0, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System
3F0802-03, License Amendment Request 271, Revision 0 Re One Time 24-hour Delay for Entry Into Improved Technical Specification 3.0.3 from Crystal River Unit 3
3F0902-06, Florida Power, Crystal River Unit 3 - License Amendment Request 271, Revision 1, Revised Improved Technical Specification (ITS) 3.7.18, for Two Inoperable Control Complex Chillers
CY-01-012, License Amendment Request 270, Revision 0, Power Uprate to 2568 Mwt
05000313/LER-1989-002-01, :on 890120,reactor Trip Occurred Due to Failure in Main Generator Exciter & Two Reactor Coolant Pumps Tripped on Undervoltage When Bus H1 Failed to Fast Transfer to Offsite Power.Caused by Arcing in Exciter
05000302/LER-1989-023, :on 890616,startup Transformer Became de-energized Which Resulted in Reactor/Turbine Trip.Caused by Combination of Fault Detector Relay Failure & Personnel Error.Corrective Action Being Reviewed
05000302/LER-1989-010, :on 890331,determined That Electrical Cable Splices Associated W/One of Main Feedwater Pump Suction Valves Wrongly Installed.Caused by Personnel Error.Procedure Governing Splice Installation Revised
05000313/LER-1989-021, :on 890601,inadvertent Main Steam Line Isolation Occurred During Maint.Caused by Defective Instrument Modules.Defective Modules Replaced & Affected Channels Tested
05000313/LER-1987-003-01, :on 870808,emergency Feedwater Sys Actuation Occurred During Power Reduction.Caused by Main Feedwater Valve Fulcrum Pin Out of Position Due to Personnel Error.New Set Screws & Pin Installed
05000302/LER-1987-011, :on 870710,reactor Trip Occurred Due to Loss of Reactor Coolant Pump (RCP) Power Monitors.Caused by Failed Relay in RCP B Power Monitor Circuit Due to Open Power Fuse. Monitor Relay & Fuse Replaced
05000312/LER-1987-042, :on 870912,technician Detected Electrical Problems W/Amphenol Blue Ribbon Connectors.Caused by Coating of Residue from Solder Flux,Organic Matls & Plasticizers. Nonconforming Rept Procedure Revised
05000313/LER-1987-005-01, :on 870825,reactor Trip Occurred Due to Failure of One Phase of Breaker 5118.Caused by Relay Personnel Forgetting to Pull Breaker Failure Module.Maint & Testing Performed & Procedures Under Evaluation
05000302/LER-1986-008, :on 860620,following Low Level Alarm on once-through Steam Generator B,Emergency Feedwater Sys Automatically Actuated.Caused by Low Water Level Due to Spurious Closing of Startup Control Valve
05000313/LER-1987-004, :on 870815,reactor Trip & Emergency Feedwater Actuation Occurred During Power Ascension Due to Main Feedwater Pumps Control Sys Problems.Caused by Placing Pump in Automatic Control at Power Level Too Low
05000313/LER-1997-003-03, :on 970708,inadvertent Automatic Actuation of EFW Sys Occurred.Caused by Tripping of EFIC Channel D Power Supplies Coincidental W/Loss of FW Pumps.Rps Testing Secured & All Trips Reset
05000313/LER-1999-313, :on 990911,AI of EFWS Occurred During Plant Shutdown as Result of Securing Running RCPs Due to Reverse Rotation of Idle Pump.Caused by Failure of Motor anti-rotation Device.Device Was Replaced.With
05000302/LER-1997-026, :on 970814,failure to Perform Field Validation Resulted in Deviation to 10CFR50 App R Requirements.Caused by Inadequate Incorporation of App R Fire Study Requirements.Will Reroute Affected Conductors
05000313/LER-1987-002-01, :on 870516,problems Encountered W/Main Turbine electro-hydraulic Control During Electrical Storm.Caused by Defective Analog Comparator Card.On 870517,turbine Tripped Upon Insertion of New Card.Plant Stabilized
05000312/LER-1987-004, :on 870114,fire Watch Prematurely Removed in Violation of Tech Specs.Caused by Central Alarm Station Operator Error.Operator Removed from Duties & Assigned as Field Sergeant as Disciplinary Measure
05000302/LER-1987-001, :on 861231,half-trip Signal Received on Main Steam Line Isolation Channel A.Caused by Faulty Light Emitting Diode (Led).On 870101,Tech Spec 3.0.3 Voluntarily Entered to Replace Led
05000312/LER-1988-015, :on 881014,reactor Tripped Due to Grid Disturbance.Caused by Transmission Line Faults.Phase to Phase Fault Protection Extended Past Stagg Substation
05000302/LER-1987-002, :on 870221,during Monthly Surveillance of Emergency Feedwater Initiation & Control Sys,Technicians Unable to Place Channel B in Bypass for Maint & Testing. Caused by Failure of light-emitting Diode
05000302/LER-1986-016, :on 860930,spurious half-trip Signal Received. Caused by Faulty light-emitting Diode in Emergency Feedwater Initiation & Control Sys.On 861001,Tech Spec 3.0.3 Entered to Replace Diode & Test Sys.Sys Operable
05000302/LER-1999-003, :on 950902,operation Prohibited by ITS Was Noted.Caused by Inadequate Development of Instrumentation Specification.Issued Short Term Instruction & Clarification of ITS Bases.With
05000312/LER-1988-011, :on 880806,dual-drive Auxiliary Feedwater Pump P-318 Shut Down Due to Outboard Packing Overheating.Caused by vendor-supplied Packing Being Dimensionally Incorrect.New Style of Packing Installed in Outboard Gland
05000302/LER-1985-026, :on 851122,feedwater Transient Resulted in Emergency Feedwater Initiation & Control (EFIC) Sys Actuation & Reactor Trip on High RCS Pressure.Further Training on EFIC Sys Provided to Operators
05000302/LER-1985-027, :on 851123,spurious Actuation & Loss of Emergency Feedwater Occurred During Calibr of once-through Steam Generator Level Instruments.Caused by Pressure Surge. Changes to Actuation Circuitry Being Considered
05000302/LER-1997-011, :on 970529,pressure Locking of EFWS Isolation Valves Resulting in Potential for Interruption of EFW Flow to SG Occurred.Caused by Inadequate Calculation.Procedure for Preparation of Calculations Revised
05000302/LER-1985-033, :on 851226,automatic Functions of Emergency Feedwater Initiation & Control Sys Rendered Inoperable to Preclude Spurious Actuation Due to Defective once-through Steam Generator Low Level Initiate Bistable
05000302/LER-1985-022, :on 851013,half-trip Signal Received on Channel B of Emergency Feedwater Initiation & Control Sys for Main Steamline Isolation from once-through Steam Generator B. Source of Signal Could Not Be Determined
05000313/LER-1985-011, :on 851001,manual Reactor Trip Occurred on Inadvertent Closure of Main Steam Block Valve.Caused by Loose Relay Cover Resulting from Wiring Terminations to Relays.Wiring Corrected
05000302/LER-1985-020, :on 851009,both MSIVs from Steam Generator B Automatically Closed Due to Spurious Emergency Feedwater Initiation & Control Actuation.Caused by Low Steam Generator Level Indication.Trip Module Replaced
05000302/LER-1985-023, :on 851026,turbine/reactor Trip Occurred & Automatic Runback Initiated.Control Board Operation Manually Tripped Main Turbine,Resulting in Anticipatory Reactor Trip. Caused by Defective Oscillator Board
05000302/LER-1985-012, :on 850809-16,low Steam Generator Level Feature of Emergency Feedwater Initiation & Control Sys Actuated 12 Times.Caused by Insufficient Margin Between Normal Level Control & Low Level Actuation Setpoints
05000302/LER-1997-005, :on 970214,discovered Unanalyzed Condition Re Emergency Feedwater Sys & Small Break LOCA Mitigation.Caused by Misunderstanding of Reliance on Emergency Feedwater.Will Upgrade EDGs & Develop Mitigation Strategies
05000302/LER-1985-028, :on 851203,fault of 6,900-volt Bus Caused Loss of Reactor Coolant Pumps Resulting in Reactor Trip.Caused by Loose Connector on Bus Side of Motor Breaker RCP-10. Switchgear Repaired.Connectors Tightened
05000302/LER-1985-029, :on 851204,Channel B of Emergency Feedwater Initiation & Control Sys Could Not Be Electrically Switched Into Maint Bypass & All Automatic Functions Rendered Inoperable.Caused by Failed Module
05000302/LER-1985-013, :on 850815,unit Experienced Inadvertent Partial Actuation of Emergency Feedwater Initiation & Control Sys. Caused by Unplanned Shutting of Main Steam Valve MSV-159 in Response to Steam Leak on Valve VI
05000302/LER-1997-001, :on 970128,cavitation from Inadequate NPSH Affected Availibility of Efp.Cause by Ineffective Configuration Change Management.Edg a Power Upgraded,Efw Sys Mods & Failure Modes & Effects Analyzed
05000302/LER-1996-024, :on 961011,plant Mod Created Unanalyzed Condition Re Emergency Feedwater Availability.Caused by Inadequate Translation of Assumptions from Earlier Designs. Design Basis Documents Were Corrected
3F1296-19, Informs of Efforts to Address Weaknesses & to Briefly Give Status of Planned Improvements in Response to Insp Rept 50-302/96-15
05000302/LER-1985-014, :on 850816,two Actuations of Emergency Feedwater Initiation & Control Sys Occurred Due to Low Steam Generator Level.Caused by Temporary Imbalance Between Feed & Steam Flow Levels Due to Operator Error
05000302/LER-1996-020, :on 960910,identified Unreviewed Safety Question Re Diesel Generator Loading.Caused by Personnel Error in Interpreting Regulatory Requirements.Imposed Startup Restraint
05000302/LER-1992-015, :on 920717,EFIC Sys Actuation Occurred Due to Low OTSG Level.Plant Startup Procedure Will Be Revised to Assure That Both Main Feedwater Pumps Are Capable of Controlling Main Feedwater Flow
05000302/LER-1996-017, :on 960531,reactor Tripped on High Reactor Coolant Pressure During Turbine Testing.Caused by Debris in Manual Isolation Valve.Post Trip Analysis Performed & Request for Engineering Assistance Initiated
3F0796-03, Forwards Action Plan to Upgrade Design of Post-Accident Monitoring Instrumentation
05000302/LER-1996-009, :on 960327,failure to re-attach Instrument Tubing to Seismic Supports After Mod Leads to Operation Outside Design Basis Occurred.Caused by Personnel Error. Instrument Tubing Properly Supported
05000302/LER-1995-016, :on 950831,revised Calculations Lead to non- Conservative EFIC Setpoint That Resulted in Operation Outside Design Basis.Caused by Change in Methodology Used by Util Personnel.Changed EFIC Sys
05000302/LER-1995-015, :on 950830,revised Calculations Lead to non- Conservative EFIC Setpoint That Resulted in Entry in ITS 3.0.3.Caused by Change in Methodology Used by Util Engineering Personnel.Changed EFIC Setpoints
05000302/LER-1990-018, :on 901128,TS 3.0.3 Voluntarily Entered Due to Apparent Increasing Leak on Nuclear Svcs Raw Water Pump Common Discharge Header.Caused by Localized Galvanic Corrosion.Leaking Assembly Replaced
05000302/LER-1991-016, :on 911125,loss of Intergrated Control Sys Power Experienced.Cause Unfounded.Control of Feedwater Sys Regained
05000302/LER-1991-014, :on 911125,feedwater Booster Pump Tripped. Caused by Gasket Failure.Technicians Replaced Gaskets W/ Different Type Gasket
05000302/LER-1982-076-03, /03L-0:on 821220,feedwater Ultrasonic Flow Indicator FW-313-FI & Emergency Feedwater Train B Discovered Inoperable.Caused by Excessive Heat in Emergency Feedwater Line.Line Cooled.Indicators Will Be Replaced
05000302/LER-1994-004, :on 940701,noticed That ATWS Turb AMSAC Low Flux Bypass Annunciator Began to Alarm Every Few Seconds Due to Personnel Error.Setpoints for ATWS-AMSAC Arming Reset & Surveillance Performed
05000313/LER-1994-002-03, :on 940411,reactor Automatically Tripped.Caused by Over Voltage Condition.Power Restored to EFIC Channel of B & D by Opening Breaker for Channel & Allowing Protective Devices to Reset
05000302/LER-1982-067-03, /03L-0:on 821028,feedwater Ultrasonic Flow Indicator FW-313-FI Discovered Inoperable.Caused by Defective Scale Card.Scale Card Replaced & Functional Check Satisfactorily Completed
05000302/LER-1982-068-03, /03L-0:on 821029,feedwater Ultrasonic Flow Indicator FW-312-FI Found Inoperable During Daily Surveillance,Rendering Emergency Feedwater Train a Inoperable.Caused by Insufficient Cable Clearance
05000313/LER-1990-016-03, :on 901127,reactor Protection Sys & Emergency Feedwater Initiation & Control Sys Setpoints Not Calibr,Per Tech Specs Requirements.Caused by Personnel Error
05000313/LER-1994-001-03, :on 940201,inoperable Emergency Feedwater Sys Flowpath Occurred.Caused by Operators Inattention to Detail While Taking & Reviewing Logs.Operations Shift Mgt & Crew Meeting to Discuss Lessons Learned from Event
1CAN058206, Updates Status of Util Efforts to Upgrade Emergency Feedwater Sys.Final Installation Will Be No Later than Fall 1984
3F0793-02, Forwards SG Tube Pull Results.Recommends Meeting W/Nrc to Discuss Results & Util Plans for Refuel 9
3F0393-02, Forwards Response to Suppl 1 to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Approx 82 Transmitters Identified Which Fall within Scope of Suppl
3F0690-03, Forwards Info Re Fire Protection Sys Reliability for Providing Water to Intermediate Bldg Following High Energy Line Break.B&W Issued Contract to Verify Mass/Energy Release & Motor Starters & Terminal Blocks Insulated
3F0390-27, Provides Supplemental Response to Station Blackout Rule Implementation & Affirms That Diesel Generator Target Reliability Will Be Maintained
05000313/LER-1991-003-02, :on 910421,actuation of EFW Sys During Plant Heatup Occurred Due to Low Once Through Steam Generator Level.Caused by Leaking Feedwater Recirculation Valve.Plant Startup Procedure OP 1102.02 Will Be Revised
05000302/LER-1990-003, :on 900220,instrument Fluctuation Noted During Surveillance of Chilled Water Pump.Caused by Location of Flow Element within Chilled Water Sys.Relief Request Submitted & Field Problem Rept Generated
1CAN039001, Responds to Generic Ltr 89-19 Re USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. Individual Plant Exam Approach Will Result in Best Safety Solution to Generic Ltr 89-19 & Listed NUREGs
NL-88-223, Monthly Operating Rept for Jan 1988
1CAN081801, Response to Request for Additional Information Related to License Amendment Request - Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves
0CAN031802, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06,.
05000313/LER-1998-004-04, :on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With
05000313/LER-1917-001, Regarding Automatic Start of an Emergency Diesel Generator Due to the Loss of Offsite Power Due to Severe Weather
05000313/LER-2016-002, Regarding Tornado Missile Vulnerability Resulting in Condition Prohibited by Technical Specifications
3F1112-06, Response to Recommendation 2.3, Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident
3F1011-05, Calculation 86-9168766-001, CR-3 EPU Inadvertent Engineered Safeguards Actuation (Iesa) Analysis Summary
05000302/LER-2009-003, Regarding Manual Reactor Trip Due to Group 7 Control Rods Insertion Caused by Inadequately Protected Test Jumper
3F0909-04, Response to Requests for Additional Information for the Review of the License Renewal Application and Amendment 3
3F0509-01, Response to Request for Additional Information for the Review of the License Renewal Application
05000302/LER-2009-001, Re Manual Reactor Trip Due to Loss of a 4160V Unit Bus Loads Caused by Incorrectly Connected Test Leads
3F1208-02, Systems Drawings Supporting License Renewal
05000302/LER-2008-003, Manual Reactor Trip Due to Main Feedwater System Oscillations Caused by an Inconsistent Procedure
05000302/LER-2008-002, Emergency Feedwater Actuation on Low Steam Generator Level Due to Feedwater Pump Speed Tuning
3F0607-05, License Amendment Request 296, Revision 1, Measurement Uncertainty Recapture Uprate
3F0407-10, License Amendment Request 296, Revision 0, Measurement Uncertainty Recapture Uprate
05000313/LER-2005-003, Unit 1, Re Reactor Trip Due to Automatic Actuation of the Reactor Protection System on Main Turbine Trip and Invalid Actuation of the Emergency Feedwater System
TSTF-05-16, TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
3F0105-02, License Amendment Request 289, Revision 0 Revised Improved Technical Specifications 3.5.2, Emergency Core Cooling Systems - Operating, 3.6.6, Reactor Building Spray & Containment Cooling Systems, 3.7.8, Decay Heat Closed Cycle
05000302/LER-2003-002, Regarding Main Steam Safety Valve Setpoints Below Required Tolerance Longer than Allowed by Technical Specifications
CEO-88-296, Forwards Response to Violation Noted in Insp Rept 50-312/88-23.Corrective Actions:Maint Engineers Will Be Reinstructed on Plant Procedures Re Configuration Control, Including Temporary Mods
3F0984-04, Clarifies Statement on Page 1-8,Item D of Safety Evaluation of Emergency Feedwater Sys Upgrade,Per NUREG-0737,Item II.E.1.1.Air Operated Valves Not in Use.Motor Operated Valves Will Be Determinated in Locked Open Position
05000302/LER-1997-024, :on 970731,feedwater Valves Did Not Meet Requirements for Main Steam Line or Feedwater Line Break Event Mitigation.Caused by Inadequate Design & Calculation Errors.Fsar Will Be Updated by 971130
05000312/LER-1986-017, :on 860826,discovered That Plant Operated Outside Tech Specs Since 1983.Condition Could Have Caused Failure of Safety Sys Train in Event of Large Break Loca. Proposes Installation of Diesel Generators
05000302/LER-1995-023, :on 951027,engineering Personnel Determined Bldg Spray Flow Valves Used in Various Engineering Calculations Inconsistent.Caused by Design Analysis Deficiency.Problem Rept Issued
05000313/LER-1989-022, :on 890120,RCS Backleakage Occurred Through failed-open Check Valve Resulted in Design Temp of Hpis Piping Being Exceeded.Caused by Failure of Support Designer to Use Correct Load.New Support Replaced
05000313/LER-1989-019-01, :on 881209,emergency Feedwater Initiation & Control Sys Actuation Occurred on Indicated Low Water Level. Caused by Personnel Error.Memo Issued Describing Event & Recognition of Need for Valve Use Emphasized