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 Issue dateTitleTopic
05000311/LER-1990-0269 July 1990LER 90-026-00:on 900609,radiation Monitoring Sys Channel 2R12B Failed Low.Caused by Design/Equipment Concerns.Failed Components Replaced & Pins Connecting Backplane Replaced W/Longer pins.W/900709 Ltr
05000311/LER-1990-02717 July 1990LER 90-027-00:on 900628,determined That ESF Signal Actuation 2R41C Channel Failed Low Due to 2R45 Interlock.Caused by Design/Equipment Concerns.Engineering Investigated Concerns & Uninterruptable Power Sys installed.W/900717 Ltr
05000311/LER-1990-03024 July 1990LER 90-030-00:on 900703,ESF Actuation Containment Purge/ Pressure Vacuum Relief Sys Isolation Occurred After Channel Function Not Placed in Block.Caused by Personnel Error. Individuals Involved Held accountable.W/900724 Ltr
05000327/LER-1982-0701 July 1982LER 82-070/01T-0:on 820618,discovered Possible Inoperability of Containment Sump Level Instrument Loops in Event of Loca.Possibly Caused by Increased Temps Rupturing Sensor Bellows.Procedures Revised
05000327/LER-1982-126, Revised LER 82-126/01T-1:on 821105,check Valve Downstream of MSIV Failed.Caused by Valve Disc Separating from Stem & Lodging Downstream in Steam Dump Header.Disc Retrieved & Replaced30 March 1983Revised LER 82-126/01T-1:on 821105,check Valve Downstream of MSIV Failed.Caused by Valve Disc Separating from Stem & Lodging Downstream in Steam Dump Header.Disc Retrieved & Replaced
05000327/LER-1983-122, Updated LER 83-122/03X-1:on 830927 & 28,diesel Generator 2A-A Declared Inoperable Due to Failure to Maintain Load of 4,400 Kw During Surveillance Testing.Caused by Faulty Exciter1 November 1983Updated LER 83-122/03X-1:on 830927 & 28,diesel Generator 2A-A Declared Inoperable Due to Failure to Maintain Load of 4,400 Kw During Surveillance Testing.Caused by Faulty Exciter
05000327/LER-1993-01911 August 1993LER 93-019-00:on 930713,containment Isolation Occurred Due to Inaccurate Drawing Used to Develop Clearance Boundary. Returned Valves to Normal Positions & Restored Sys Air pressure.W/930811 LtrSafe Shutdown
05000327/LER-1993-02017 August 1993LER 93-020-00:on 930719,Train B of Auxiliary Bldg Gas Treatment Sys Manually Initiated as Result of Fire in General Supply Fan Room.Sg Wet Layup Recirculation Pump Bearing & Motor replaced.W/930817 LtrFire Watch
05000327/LER-1993-02118 August 1993LER 93-021-00:on 930720,discovered That Boron Analysis of Refueling Canal Not Performed,As Required by TS 3.9.1 Due to Miscommunication.Lco 3.9.1 Entered.Chemistry Surveillance Instruction Will Be revised.W/930818 Ltr
FVY-86-105, Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl10 November 1986Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl
IA-84-843, Safety Evaluation Supporting Amend 25 to License DPR-7530 August 1984Safety Evaluation Supporting Amend 25 to License DPR-75Fire Barrier
Nondestructive Examination
Liquid penetrant
IR 05000311/197901910 November 1979Updated LER 79-054/01X-1:on 790824,three Snubbers on Main Feedwater 14 During Refueling Outage Per Followup to NRC Insp Rept 50-311/79-19.Caused by Extreme Shock Load.Snubbers Replaced
L-97-215, SG Secondary Side Loose Object Safety Evaluation23 October 1997SG Secondary Side Loose Object Safety Evaluation
ML17208B0783 April 1980Monthly Operating Rept for Mar 1980
ML17264A93810 July 1997Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process
ML17346B35511 March 1986LER 86-004-00:on 860209,required Plant Vent Sampling Not Performed.Caused by Inadequate Means of Scheduling Samples Required by Radiological Eis.Training Programs Updated. W/860311 Ltr
ML17348B49331 July 1990Monthly Operating Rept for Jul 1990 for Salem 2.W/900815 LtrBoric Acid
ML17354B0979 September 1998Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils
ML18033B74231 July 1988Monthly Operating Repts for Jul 1988 for Sequoyah, Units 1 & 2.W/880811 LtrBoric Acid
Shutdown Margin
Loop seal
Offsite Dose Calculation Manual
Stroke time
ML18037A48531 December 1992Annual Rept 1992, for Bfn,Units 1,2 & 3 & Sequoyah Nuclear Plant,Units 1 & 2
ML18038A8977 September 1994Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures
ML18078A2273 October 1978LER#78-062/03L-0 on 780913:during Normal Oper the #12 Reactor Coolant Flow Channel 2 Was Not Indicating Due to Failure of a Hagan Controls Signal Isolator
ML18078A2343 October 1978LER#78-064/03L-0 on 780912:reactor Trip Setpoint Greater than T/S Limit During Check of Pressure Protec Channel 2. Caused by Unstable Output from Comparator Feeding Trip Bistable.Comparator Replaced
ML18078A24410 October 1978Monthly Operating Rept for Sept 1978
ML18078A31923 October 1978RO 78-70/01P:on 781021,reactor Coolant Pump 13 Shaft Seals Failed,Resulting in Excessive Leakage of Primary Coolant Into Containment.Detailed Rept Will Follow
ML18078A32124 October 1978Confirms 781024 Verbal Rept of Ro.Low Pressure in Control Air Sys Caused Operation of Air Operated Deluge Valves, Necessitating Operation of Fire Pumps in Manual Mode.Ler Will Follow
ML18078A32626 October 1978LER 78-067/03L-0:on 780929,missing Fire Barrier in Cable Penetration Identified.Caused by Failure to Ensure Fire Barrier Installation.Cable Penetration Immediately Sealed. Other Barriers Will Be Inspected by 781101Fire Barrier
Continuous fire watch
Fire Watch
ML18078A3472 November 1978LER 78-070/01T-0:on 781021,during Mode 4 Operation,While Heating Up to Enter Mode 3,high Flow Through RCP Seals Noted & Alarms Went Off Indicating RCS Leakage.Cause UnknownPressure Boundary Leakage
ML18078A3501 November 1978LER 78-071/01T-0:on 781023:during Mode 5,fire Pumps 1 & 2 Put in Manual Due to Low Air Pressure Causing Actuation of air-operated Deluge Valves.Station Air Compressors Could Not Be Started Due to Low Cooling Water FlowFire Watch
ML18078A3532 November 1978LER 78-069/03L-0:on 781011,while Investigating Diesel 1B Alarm,Heater Leaking Chromated Water Into pre-lube Pump Motor Discovered.Caused by Corrosion of Element Sheath in Two of Three Heater Elements
ML18078A37623 October 1978RO 78-70/01P:on 781021,#13 Reactor Coolant Pump Shaft Seals Failed,Resulting in Excessive Leakage of Primary Coolant Into Container.Detailed RO Rept Will Be Submitted
ML18078A3899 November 1978Monthly Oper Rept for Oct 1978
ML18078A39914 November 1978LER#78-043/03L-1 on 780808:as Reactor Pwr Was Increased a Deviation Alarm Would Not Clear & a Qpt Calculation Showed a QPTR of 1.03%.Due to Large Load Reduction.Design Change Will Delete the Less than 50% Pwr Alarm
ML18078A41220 November 1978LER#78-072/01T-0 on 781106:during Mode 5 Oper,All Containment Fan Coil Units Were Found Inoper Due to Tripped Svc Water Valves,Caused by Design Deficiency in Detector Installation
ML18078A41520 November 1978Answers NRC Questions 5.62,5.63,5.82,5.83,5.84 & 5.85 Re Analyses of Main Steam Lines Break within Containment of Unisolated Steam in Main Steam Line & Turbine Plant
ML18078A45222 November 1978LER#78-043/03L-0 on 780808:during Normal Oper,After 45% Pwr Reduction to Less than 50% for Maint,Reactor Pwr Increased to 51%.Deviation Alarm Would Not Clear & QPTR Was 1.03%.QPTR Was Not Discovered Sooner Because of Alarm Indications
ML18078A4919 November 1978Monthly Rept Oct 1978
ML18078A49711 December 1978LER#78-073/01T-0 on 781127:1B Vital Instru Bus Was Lost Causing Reactor Trip.Safety Injection Followed & 1B Diesel #11 Charging & #12 RHR Pumps Failed to Start.Caused by Bad Output Transformer in Supply Inverter
ML18078A50311 December 1978Monthly Oper Rept for Nov 1978Packing leak
ML18078A53118 December 1978LER#78-075/03L on 781130:during Oper W/Containment Entry in Progress,Inner Door of Air Lock 130 Would Not Fully Open, Caused by Failed Cam Roller on Inner Door Operating Mechanism.Air Lock Repaired,Tested,Returned to Svc
ML18078A57726 December 1978LER 78-077/03L-0 on 781128:pressurizer Level Read 10% Higher than Other Channels.Calibr of Sensor Showed Tech Spec Limit for Low Level Trip Was Exceeded by 2% Due to Failure of Strain Gauge in Pressurizer Level Sensor
ML18078A58128 December 1978LER 78-078/03L-0 on 781130:channel Checks Showed Deviation Between Steam Flow Channels I & II of Steam Generator 13. Caused by Transmitter Zero Shift
ML18078A59128 December 1978LER 78-079/03L-0 on 781201:steam Generator 12,level Channel III Found to Be Inoperable;Channel Bistables Tripped Per Tech Specs.Caused by Partially Clogged Sensing Lines
ML18078A6144 January 1979LER 78-081/03L-0 on 781206:noted That Sump Pump Magnetrol Was Overdue for Calibr.Caused by Incorrect Assignment of Responsibility for 18 Month Calibr Surveillance
ML18078A6203 January 1979LER 78-076/03L-0 on 781208:during Surveillance of Meteorological Instruments,Noted That Normal Power Had Failed & Inverter Had Not Shifted to Batteries.No Cause for Failure Discerned;Inverter Tested Satisfactorily
ML18078A63910 January 1979LER 78-083/03L-0 on 781213:Number 13 Auxiliary Feed Pump Tripped on Overspeed Because Governor Operating Speed Was Set at 4200 Rpm.Governor Speed Reset & 3 Tests Confirmed Operability
ML18078A64210 January 1979Monthly Operating Rept for Dec 1978Boric Acid
Packing leak
ML18078A64510 January 1979LER 78-085/03L-0 on 781211:svc Water Flow Through Fan Coil Unit Was Less than Required 2500 Gal Per Minute.Caused When Solenoid Control Coil Developed an Open Circuit
ML18078A67015 January 1979LER 78-080/03L-0 on 781228:leak Rate Test Showed Excessive Seal Leakage & Air Lock Was Declared Inoperable.Caused by Failure of Outer Door Seal from Normal Wear of the Seal During Air Lock Operation
ML18078A67312 January 1979Evaluation of the Reactor Coolant Sys Considering Subcompartment Pressurization Following a LOCA for Unit Re Conversion of Transient Mass Distribution Code Pressures to Forces, & Interior Concrete Structures
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