RA-17-072, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition
BVY 09-052, Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves
05000296/LER-1997-005-02, :on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed
05000281/LER-1991-014, :on 910724,determined That Scaling for Main Steam Flow Transmitters Incorrect,Resulting in Setpoints in Excess of Max Allowed Value of 110%.Caused by Use of Incorrect Methodology.Scaling Program Underway
L-MT-04-003, License Amendment Request for Technical Specification Table 3.2.3 and Section 3.7/4.7
L-MT-03-085, Technical Specification Bases Pages Changes
B13146, Responds to NRC Questions Re Vacuum Breakers from Torus to Reactor Bldg
JPN-87-044, Proposed Tech Specs,Allowing Plant Operation for Remainder of Cycle 8 W/Min MSIV Closure Time of 2 for One of Four Steam Lines
JAFP-98-0137, Provides Rev to 980225 Response to NRC Re NOV from Insp Rept 50-333/97-08 on 971027-1221.Corrective Actions:Performed Root Cause Evaluation
B17621, Application for Amend to License DPR-21,reflecting Permanently Defueled Condition of Unit 1,Tech Specs Administrative Controls Section as Allowed by Guidance Contained in NRC Administrative Ltr 95-06
JAFP-98-0074, Responds to NRC Re Violations Noted in Insp Rept 50-333/97-08 on 971027-1221.Corrective Actions:Operations Manager Has Reviewed Results of Root Cause Evaluation W/ Operations Shift Personnel
NG-92-5179, Request for TS Change RTS-249 to License DPR-49,adding TS 3.0 & 4.0,corresponding Bases & Modifying Existing Specs Consistent W/New Requirements Denoting Applicability of LCOs & Srs,Per STS & GLs 87-09 & 89-14
BECO-85-082, Documents Withdrawal of 850404 Proposed Change to Tech Spec 3.7.D.2,due to Repair of Inboard Sample Line Isolation Valve A0220-44.Proposed Change Verbally Withdrawn in 850404 Telcon
JAFP-96-0168, Annual Summary of Changes,Tests & Experiments for 1995. W/
JAFP-92-0470, Ja Fitzpatrick Nuclear Power Plant Annual Summary of Changes,Tests & Experiments for 1990
BECO-85-067, Application for Amend to License DPR-35,adding Footnote to Tech Spec Section 3.7.D.2,granting Temporary Relief to Allow Hydrogen Injection Testing
BECO-84-197, Informs That Existing Purge/Vent Related Tech Specs Per TMI Item II.E.4.2 Conform W/Model Tech Specs Supplied as Attachment 4 of .Installation of Different Valves Does Not Require Tech Spec Amend
BVY-95-110, Forwards Missed Safety Evaluation Summaries Re Cycle 16 Operating Rept as Required by 10CFR50.59(b)(2)
JAFP-92-0140, Responds to NRC Re Violations Noted in Insp Rept 50-333/91-21 on 911027-1214.Corrective Actions:Core Spray Pump Running Permissive Installed in Min Flow Bypass Valve Logic Circuit of Core Spray Min Flow Valves on 911205
NG-94-3575, Request for TS Change (RTS-267),replacing Instrument Setpoint W/Ref to Appropriate Citation in Offsite Dose Assessment Manual & Modifying Operability Requirement & Required Action for Inoperable Offgas Vent Stack RMs
05000278/LER-1983-006, Forwards LER 83-006/01T-0.Detailed Event Analysis Submitted
05000271/LER-1989-022, :on 890831,identified That Outboard Isolation Valve V70-117 Fed from Nonemergency Power Bus.Exact Root Cause Unknown But Design Spec Misinterpretation Suspected. Temporary Mod Implemented
05000254/LER-1989-008-02, :on 890607,during Quarterly fail-safe Testing, Valve 1-1601-23 Would Not Fail Closed on Loss of Instrument Air.Caused by Use of Colorflow Control Valve Instead of Check Valve.Valve to Be Replaced
05000333/LER-1989-008-01, :on 890517,surveillance Testing of HPCI & RCIC Auto Isolation Sys Time Delay Devices Not Completed as Required by Tech Spec Table 4.2-2.Caused by Procedure Deficiencies.Tech Spec Changes Submitted
05000333/LER-1999-008-01, :on 990910,HPCI Sys Was Declared Inoperable Due to Apparent Failure of Master Trip Unit (MTU) within HPCI Sys Automatice Isolation Logic.Subject MTU Was Replaced & HPCI Sys Was Returned to Operable Status.With
05000298/LER-1986-018, :on 860818,reactor Water Not Sampled for Conductivity After Reactor Recirculation Sys Inboard Sample Valve Declared Inoperable Due to Failed Solenoid Valve. Caused by Personnel Error.Personnel Counseled
BVY 09-067, Response to Request for Additional Information Related to Technical Specifications Proposed Change No. 284 Change to Requirements for Inoperable Containment Isolation Valves
05000333/LER-1986-003, :on 860312,HPCI Outboard Steam Supply Valve Bypass Valve 23-MOV-60 Failed to Operate Properly During Surveillance Testing.Caused by Corrosion of Clutch Mechanism.Parts Replaced & Drive Shaft Cleaned
05000333/LER-1997-011-01, :on 971024,invalid ESF Actuation & Failure to Perform TS Required Actions Occurred While Performing Required Actions While Troubleshooting Activities.Restored HPCI Sys to Normal IAW Plant Procedures
05000298/LER-1997-019, :on 971222,incorrect Mind Set & Scheduling Process Resulted in TS Violation.Caused by Failure of Shift Supervisor Support.Problem Identification Rept Associated W/ Event Will Be Presented as First Case Study
05000333/LER-1997-013-01, :on 971216,high Pressure Coolant Sys Was Declared Inoperable.Caused by Instrument Malfunction During Surveillance Testing.Completed Repair Activities to Correct Adjustments to Master Trip Unit
05000277/LER-1985-024, :on 851103,blocking Removed from Drywell Oxygen Analyzer Lines a & C Before Valves Repaired & Tested.Caused by Operator Failure to Ensure Inoperable Isolation Valve Properly Tested.Blocking Restored
05000331/LER-1986-003, :on 850809,maint Performed on Transverse in-core Probe (TIP) Ball Valve C Which Could Have Resulted in Loss of Primary Containment Integrity.Caused by Incorrect Updated FSAR Analysis
05000321/LER-1985-036-01, :on 851120,reactor Water Cleanup Inboard Isolation Valve Closed in 34 S,Exceeding Max Operating Time of 30 Per Tech Spec Table 3.7-1.Procedure 52-GM-MEL-022-OS Initiated
05000321/LER-1985-045, :on 851129,excess Flow Check Valve 1B21-F051C Failed to Check Flow.Valve Will Be Replaced During Outage & Will Be Functionally Tested During Next Reactor Startup
05000277/LER-1985-024-01, :on 851103,blocking Applied to Drywell Oxygen Analyzer Lines a & B Removed Before Inoperable Primary Containment Isolation Valves Repaired.Caused by Personnel Error.Blocking Restored
05000298/LER-1996-015, :on 961025,declared Reactor Valves Inoperable Due to Potential for Single Active Failure.Caused by Inadequate Plant Mod.Performed Assessments on Valves & Will Correct Design of Pneumatic Supplies
05000265/LER-1985-019-05, :on 850908,MSIV Closure Times Failed to Meet Tech Spec Requirement & Shutdown Commenced.Caused by Incorrect Control Valve Adjustment on Hydraulic Control Cylinder.Valves Readjusted
05000265/LER-1985-014-06, :on 850531,full Scram Initiated During Surveillance Test Q0S 1600-11 W/Unit in Shutdown Mode.Caused by Inadequacy of Procedure.Scram Reset & Procedure Q0S 1600-11 Corrected
05000321/LER-1992-014, :on 920522,reactor Scram on Turbine Stop Valve Closure Occurred Due to Turbine Stop Valves Unexpectedly Closing.Caused by Mfg Error.Ehc Sys Filter Replaced W/ Correct Type & Reservoir Filled W/New Fluid
05000321/LER-1992-011, :on 920507,control Switch for EFCV 1B21-F051C Found in Open Position,Rendering EFCV Inoperable.Caused by Inadequate Procedure.Clearance Tags Placed on Control Switches for EFCVs & Procedure Revised
05000333/LER-1992-018, :on 920407,discovered Potential Failure of Containment Isolation Valves in RHR Pump min-flow Lines to Close.Caused by Design Error.Internal Parts of Valves Will Be Replaced Prior to Startup
05000333/LER-1992-005, :on 920122,remote Manual Closing of Primary Containment Isolation Valves for HPCI & RCIC Pump Suction Lines Defeated.Caused by Inadequate Operating Review.Design Reviews & Mod of Control Circuits Set Up
05000333/LER-1992-003, :on 920108,during Cold Shutdown Incorrect Motor Pinion Key Discovered in Core Spray Sys Injection & Primary Containment Isolation Valves.Caused by Vendor Error in Part Number.Correct Key Installed
05000333/LER-1991-028, :on 911128,reactor Shutdown & Cooldown Was Not Completed within Time Required.Caused by Personnel Error. Operating Procedure 65 Will Be Revised & Event Will Be Discussed W/Licensed Operators
05000333/LER-1991-026, :on 911127,Train a & B Core Spray Pump Min Flow Valves Declared Inoperable.Cauesd by Inadequate Initial Onsite Review of Nuclear Svcs Info Ltr SIL 414,unclear Design Basis & Inappropriate Mod Priority
05000254/LER-1990-021, :on 900812,RHR Valve 1001-50 Failed to Open During Shutdown Cooling & Startup Operations.Caused by Thermal Binding of Valve & Hydraulic Lock of Valve Operator.Valve Manually Operated
05000254/LER-1983-013-03, /03L-0:on 830319,1A MSIV Air Pilot Valve Temp Indicator Found Inoperable.Caused by Personnel Error.Wiring Error Corrected & Personnel Reprimanded
05000296/LER-1983-022-03, /03L-0:on 830321,during Routine Testing,Primary Containment Isolation Valve 3-FCV-77-2A Failed to Close. Caused by Oil Accumulation on Solenoid Valve Shaft, Preventing Air leak-off.Replacement Planned W/New Design
05000254/LER-1983-007-03, /03L-0:on 830214,suppression Chamber Nitrogen Purge Valve AO-1-1601-56 Failed to Isolate During Maint on Drywell High Radiation Monitors.Caused by Failure of Solenoid Pilot Valve.Valve Replaced
05000277/LER-1993-013-01, :on 930819,TS Violation Occurred When Primary Containment Isolation Sys Inoperable & Isolation Valve Not Isolated & Logged.Caused by Insufficient Trouble Shooting. Auxiliary Contact Replaced
05000331/LER-1980-065-03, During Surveillance Testing Suppression Chamber Purge Inlet Valve CV-4308 Would Not Cycle,As Required by Tech Spec 3.7.D.1.Caused by Sticking Operator Mfg by Miller Fluid Power
05000321/LER-1982-064-03, /03L-0:on 820718,reactor Water Cleanup Sys Primary Containment Outboard Isolation Valve Opened While Sys Inoperable.Caused by Personnel Failure to Clear Outstanding Limiting Condition for Operation Prior to Opening Valve
05000321/LER-1982-063-03, /03L-0:on 820715,inboard Reactor Water Cleanup Primary Containment Isolation Valve Found Open in Presence of Isolation Signal.Caused by Loose Electrical Connection. Loose Connection Tightened
05000254/LER-1990-021-01, :on 900812,residual Heat Removal Valve 1001-50 Failed to Open Due to Thermal Binding
05000333/LER-1989-008, :on 900517,HPCI & RCIC Declared Inoperable Causing Missed Surveillance.Caused by Procedure Deficiency. Mods Removed Time Delay Devices from HPCI & RCIC Isolation Actuation Circuits & Procedure Reviewed
05000245/LER-1982-008, Forwards LER 82-008/03L-0.Detailed Event Analysis Encl
05000271/LER-1981-036-03, /03L-0:on 811217,containment Isolation Valve CU-15 Failed to Seat Satisfactorily Per Tech Spec 4.7.D.1 During Quarterly Surveillance Testing.Caused by Failure of Closing Torque Switch.Torque Switch Will Be Replaced Next Shut
05000245/LER-1981-042, Forwards LER 81-042/03L-0.Detailed Event Analysis Encl
05000245/LER-1981-040, Forwards LER 81-040/03L-0.Detailed Event Analysis Encl
05000331/LER-1981-040-01, /01T:on 811118,personnel Attempted to Cycle Reactor Water Cleanup Sys Return Isolation Valve MOV-2740 But No Flow Change Occurred.Caused by Loose Valve Stem Clamp Set Screw & Clamp Screw Dropping Out
05000277/LER-1981-037, Forwards LER 81-037/01T-0.Detailed Event Analysis Submitted
05000260/LER-1983-030-03, /03L-0:on 830607,torus Exhaust Valve FCV-64-34 Bypass to Standby Gas Treatment Sys Failed to Operate within 5 Time Limit.Caused by Indicating Limit Switches Being Out of Adjustment.Switches Adjusted
05000271/LER-1981-022-03, /03L-0:on 810801,MSIV-80D Failed to Close When Control Switch Was Placed in Closed Position.Caused by Foreign Particle Lodged in Spool Valve,Preventing Air from Operating Main Piston.Msiv Fully Stroked
BVY-90-016, Provides NRC W/Results of Licensee Review of Design Bases & Operability Status of torus-to-reactor Bldg Vacuum Breakers
05000277/LER-1989-030-01, :0n 891126,steam Leak Discovered Coming from Packing on RCIC Injection Check Valve AO-22.Caused by Failure of Valve Stem Packing.Normal Reactor Level Restored & Mods of Valve Will Be Pursued
NG-93-5124, Revises 911211 Response to NRC Position on Operability of safety-related Dual Function Valves & Withdraws Commitment Made in .Basis for Withdrawal of 911211 Commitment to Adopt NRC Position on Operability of Subj Valves Encl
05000265/LER-1980-030-03, /03L-0:on 801031,primary Containment Valve AO-2-1601-63 Required 30-s to Close.Caused by Malfunction of Pilot Solenoid SO-2-1601-71.Solenoid Replaced & Tested
05000265/LER-1980-035-03, Drywell Equipment Drain Sump Outboard Isolation Valve AO-2-2001-16 Exhibited Erratic Closure Time.Caused by Sediment in Valve Restricting Movement.Valve Cleaned
05000333/LER-1980-080-03, /03L-0:on 801011,primary Containment Isolation Valve 10-MOV-57 from RHR to Radwaste Would Not Close When Required Operable by Tech Spec 3.7.D.Caused by Installation of Scaffolding for Mods,Disengaging Motor Operator Clutch
05000265/LER-1980-020-03, /03L-0:on 800828,during Suppression Chamber to Drywell Seperation Test,Nitrogen Makeup Valve MO-2-16057-57 Would Not Close.Caused by Grounded Windings on Valve Motor Operator.Windings Repaired & Motor Replaced
05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated
05000293/LER-1980-033-03, /03L-0:on 800701,during Test,Nitrogen Purge Valve Did Not Close within Prescribed 10-s Limit.Cause Not Stated. Stroke Length Reduced,Valve Tested Satisfactorily & Returned to Svc
05000265/LER-1980-009-03, /03L-0:on 800322,while Performing Pci Simulated Automatic Closure Initiation Test,Procedure Qos 1600-13, Transient in-core Probe 2,failed to Respond to Group 2 Isolation Signal.Caused by Dirty Contacts on Relay K21
05000259/LER-1980-025-03, /03L-0:on 800313,primary Containment Isolation Testing Revealed Failure of RHR Injection Valve 74-67 to Close Upon Isolation Signal.Caused by Limit Switch on FCV- 74-48 Not Making Good Contact.Contact Cleaned & Adjusted
05000265/LER-1978-038-03, /03L-0 on 781125:during Normal Operation,Drywell Vent Valve AO-1601-23 Would Not Open.Mechanical Failure of Solenoid Air Supply Valve SO 2-1601-52A Prevented Operation of Drywell Vent Valve.Solenoid Valve Was Replaced & Test
05000298/LER-1978-040-03, /03L-0 on 781227:during Normal Operation,While Doing Special Test of Drywell Purging Techniques,Primary Containment Vent Valve PC-246AV Leaked Excessively & Was Inoperable Due to Incomplete Valve Closure.Valve Replaced
05000278/LER-1979-018-03, /03L-0 on 790630:during Surveillance Testing, Reactor Water Sample Line Isolation Valve Failed to Close. Caused by Lack of Valve Operator Spring Tension.Valve Operator Spring Tension Was Increased
05000259/LER-1979-021-03, /03L-0:on 790902,containment Isolation Valve FCV-71-3 Would Not Close.Caused by Failure of Peerless Electric Motor S/N GV7995.Operating Limits of Valve Reset & Tested.Motor Replaced
05000296/LER-2077-017, For Browns Ferry Nuclear Plant, Unit 3, Primary Containment Isolation Valve 3-FCV-77-2A on Drywell Floor Drain Sump Pump Discharge Line Would Not Operate as Required by Tech Spec 3.7.D.L During Routine Operability Checks
05000280/LER-1992-002, On 920106,4160 Volt Transfer Buses D,E & F UV Relay Trip Setpoints Set Below TS Limits.Caused by Calibr Process Error.Relays Recalibr & Set to More Conservative Values than Required
05000280/LER-1979-003-03, /03L-0 on 790124:error Detected in Calibr Procedures for Steam Flow Instrumentation.Caused by Error Made When Calibr Procedures Changed
05000293/LER-2014-001, Regarding Condition Prohibited by Technical Specifications
L-MT-03-006, License Amendment Request for Drywell Leakage & Sump Monitoring System TS Changes
05000333/LER-1980-082-03, /03L-0:on 801102,solenoid Pilot Valve 16-1-SOV-101 B,Associated W/Containment Isolation Valve 16-1-AOV-101B, Failed Causing AOV to Fail.Caused by Worn Plunger & Dirt in Valve.Parts Cleaned & Replaced
05000277/LER-1979-030-03, /03L-0 on 790611:during Surveillance Testing of O2 Analyzer Primary Containment Isolation Valves,Valve SV2671B Failed to Close.Caused by Binding of Piston in Valve Body. Valve Internals Were Rebuilt & Test Successfully Perfo
05000254/LER-1999-003-05, :on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure
05000245/LER-1996-052, :on 960920,motor Operated Valves Unable to Close within Stroke Time Limits.Caused by Inadequate Design Margin.Performed Modifications to Ensure IC-2 Will Close & Installed Break Detection Sys Re CU-3
05000237/LER-1985-020-02, :on 850424,during HPCI Steam Line High Flow Isolation Surveillance,Hpci Valve 2301-H Failed to Close. Caused by Dirty Breaker Auxiliary Contacts.Contacts Cleaned & Later Replaced
05000296/LER-1983-028-03, /03L-0:on 830429,while Investigating Blown Fuse in Annunication,Relay 16A-K79 Failed.Caused by Coil Over Heating Melting Spool Matl & Stuck Armature in Energized Position.Relay Replaced