Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML20084R73916 January 1975AO 50-249/75-01:on 750104,insp of Bergen-Paterson Shock Suppressors Revealed Eight Snubbers Low on Oil W/Two Considered Inoperable.Caused by Pinched O-rings,slight Deterioration of Seals & Scratched Cylinder
ML20084R7686 December 1974AO 50-249/74-37:on 741201,during Routine Plant Insp,Pin Hole Leak Found on Min Flow Line.Caused by Erosion of Pipe from Within.Pipe Isolated & Leak Repaired Using Certified Welding Matls & Techniques
ML20084R7886 December 1974AO 50-249/74-36:on 741201,small Leak Discovered on Reactor Feed Pump 3A Min Flow Line 3-3205A.Caused by Erosion of Pipe.Leaking Pipe Isolated & Repaired by Welding
ML20084R8134 October 1974AO 50-249/74-47:on 740927,waste Collector Filter Pressure Switch Taps B Failed During Backwash Cycle.Lines B Bumped & Jarred During Maint on Unit A.Failed Lines Isolated
ML20084R84022 July 1974AO 50-249/74-37:on 740716,torus Oxygen Concentration Above 4% After 24 H.Caused by Nitrogen Supplier Failing to Meet Delivery.Vendor Notified & Util Advised That Original Order Had Been Lost
ML20084R85112 December 1974AO 50-249/74-35:on 741130,reactor Bldg Exhaust Fans 3A & B Tripped Off & Would Not Reset & Secondary Containment Blowout Panel Failed.Apparently Caused by Reactor Bldgs Becoming Overpressurized.Unit Shut Down
ML20084R85319 November 1974AO 50-249/74-34:on 741109,while Placing Offgas Recombiner 3A in Svc,Air Ejector Rupture Disc 3A Failed.Caused by Detonation of Offgas Which Occurred When Recombiner Outlet Valve 3A Was Opened.Steam Jet Air Ejectors Changed
ML20084R8669 October 1974AO 50-249/74-32:on 741003,high Pressure Coolant Injection High Flow Switch DPIS 3-2352 Found W/Setpoint Above Tech Spec Limit.Caused by Setpoint Drift.Switch Repaired & Reset
ML20084R8748 October 1974AO 50-249/74-31:on 740928,core Height Water Level Sensors Lits 3-263-73 a & B Found W/Setpoints Above Tech Spec Limit. Apparently Caused by Trapped Air Bubbles in Sensor or Not Considering Instrument Hysteresis
ML20084R9432 October 1974AO 50-249/74-29:on 740924,through-wall Crack Discovered on Torus/Drywell Purge Line.Cause Unknown.Segment Cut Out of Line Containing Crack & New Pipe Segment Welded in Place
ML20084R95126 September 1974AO 50-249/74-28:on 740920,leakage Noted in Feedwater Line Pressure Tap 3-3241-12A.Caused by Crack in Weld.Pressure Tap No Longer UsedTime of Discovery
ML20084R97316 September 1974AO 50-249/74-28:on 740908,following Transversing in-core Probe (TIP) Scans,Ball Isolation Valve on TIP Machine 3E Failed to Close as Indicated by Light on Control Panel. Caused by Weak Closure Spring.Plant Mod Initiated
ML20084R9993 September 1974AO 50-249/74-27:on 740928,following Surveillance of Core Spray Sys,Core Spray 3A Discharge Header Pressure Was Lost. Caused by Discharge Stop Check Valve 3-1402-8A Failure to Seat Properly.Valve Manually Cycled
ML20084S02819 August 1974AO 50-249/74-25:on 740807,ball Isolation Valve on Transversing in-core Probe Machine B Failed to Close.Caused by Broken Wire on Solenoid Coil Actuator.Top Actuator of Valve Replaced
ML20084S0511 August 1974AO 50-249/74-23 & 24:on 740726,during Insp Prior to Local Leak Rate Testing,Rubber Coated Valve Seat for AO-3-1601-21 & 22 Found Cracked.Caused by Liquid Nitrogen Reaching Both Valves.Valve AO-3-1601-21 Replaced & 22 Blank Flanged
ML20084S27420 March 1973Telecopy Ao:On 730320,waste Surge in Grand Tanks Sampled & Activity Found to Be Above Tech Spec Limit.Caused by Pumping Waste Collector Water Directly to Surge Tank. Procedures Will Be Reviewed & Revised to Eliminate Problem
ML20084S36717 January 1975AO 50-249/74-38:on 741031,excessive Power Peaking Observed in Lower Region of Core.Caused by Xenon Transient Combined W/Very Low Fuel Exposure at Core Bottom.Control Rod WithdrawnPower change
ML20084T88215 June 1970Ao:On 700605,turbine electro-hydraulic Control Sys Transient Caused Turbine Trip & Reactor Scram,Followed by Inadvertently Opened Safety Valves.Two Safety Valves Failed to Close,Releasing Primary Coolant to Containment
ML20084U0142 June 1970Ao:On 700529,piping Restraints & Supports Damaged.Caused by Displaced HPCI Steam Line Beyond Outboard Isolation Valve. HPCI Outage Time Extension Requested
ML20084U9502 January 1975AO 50-265/74-29:on 741223,cracks at Welds in 4 Inch Reactor Recirculation Discharge Valve Bypass Lines Indicated.Cause Undetermined.Piping on a & B Loops to Be Completely Replaced
ML20084U95623 December 1974Telecopy Ao:Three Weld Abnormalities Discovered on Welds in Bypass Piping Lines Around Recirculation Pump Discharge Valves.Plans Formulated to Replace Lines
ML20085G18624 October 1973Ao:On 730925,trip Setpoint of 152 Inches for HPCI Flow Switch DPIS 3-2353 Exceeded Tech Spec Limit.Caused by Locking Device Failing to Control Setpoint Drift.Switch Setpoint Changed & Calibr Frequency Increased
ML20085J8152 July 1974Ao:On 740623,severe Vibrations Experienced on Feedwater Sys, Resulting in Damage to Feedwater Regulation Valves & Pipe Restraints.Cause Unknown.Piping Repaired.Investigation Continuing
ML20085J82719 June 1974Ao:On 740611,two Reactor High Pressure Scram Switches Found W/Setpoints Above Tech Spec Limit.Caused by Instrument Drift.Program in Progress to Precondition All Barksdale & Meletron Bourdon tube-type Switches
ML20085J83918 June 1974Ao:On 740611,during Unit Startup Small Leak Detected in Line 3-3037B Which Supplies Steam to Recombiner Booster Jet B.Caused by Defective Weld.Area Rewelded
ML20085J84818 June 1974Ao:On 740610,leak Discovered in Newly Installed Vibration Test Line Located on Reactor Feedwater Pump Discharge Header.Caused by Crack on Side of Nipple of Test Line.Unit Shut Down to Repair LeakHydrostatic
ML20085J85810 June 1974Ao:On 740605,HPCI Valve 3-2301-3 Failed to Open.Caused by Lack of Clearance Between Auxiliary Contact Operating Bar & Main Contact Armature Roller.Air Gap Adjusted
ML20085J86512 June 1974Ao:On 740604,during Functional Test on Main Steam Line Radiation Monitor D,Trip & Alarm Did Not Function.Cause Unknown.Monitor Replaced
ML20085J87012 June 1974Ao:On 740603,during Routine Surveillance of Low Pressure Trip Switches PS2389 A,B,C & D Found W/Setpoints Above Tech Spec Limit.Caused by Lack of Precycling Prior to Installation.Switches Will Be Returned to Factory
ML20085J88031 May 1974Ao:On 740523,during Routine Monthly Surveillance 2/3 Core Height Water Level Sensor Lits 3-263-73A Found to Have Setpoint Above Tech Spec Limit.Caused by Setpoint Drift. Switch Reset
ML20085J89421 June 1974Ao:On 740522,main Steam Line Drain Valve 3-220-2 Failed to Operate Correctly.Caused by Burned Armature Windings in Valve Motor.Motor Replaced
ML20085J90323 May 1974Ao:On 740515,during Scheduled Refuel Surveillance All 16 Main Steam Line Temp Sensors Found to Operate Above Tech Spec Limit.Caused by Incorrect Calibr Technique.Corrective Action Dependent on Vendor Response to Problems
ML20085J92221 May 1974Ao:On 740515,during Local Leak Rate Testing of Msivs,Valves 1B & 2B Found W/Leak Rate Above Allowable Limit.Caused by Warped Valve Seat & Hairline Cracks in Stellate Overlay on Disc.Seating Surfaces of 2B Reinstalled
ML20085J93813 May 1974Ao:On 740506,during Local Leak Rate Testing of Feedwater Check valves,3-220-58B & 3-220-62B Revealed Leakage in Excess of Tech Spec Limit.Caused by O-ring Being Out of Groove.Ring Replaced
ML20085J9516 May 1974Ao:On 740427,after Rejection of Water Commenced,Torus Level Indication Increased.Operator Tapped on Impulse Lines of Transmitter & Indication Returned to Actual Level. Transmitter Calibr
ML20085J96811 June 1974Ao:Supplemental Info to Deviation Rept D-12-3-74-10 Re 3B Control Rod Drive Water Filter Drain Line.Normal Maint Insps & Sys Operational Tests Adequate to Prevent or Minimize Such Failures
ML20085J9724 April 1974Ao:On 740402,during Normal Plant Insp,Minor Leak Found in Control Rod Drive Water Filter 3B-302-4 Drain Line.Caused by Cracked Weld Due to Fatigue Failure.Crack Repaired
ML20085J9822 April 1974Telecopy Ao:On 740402,leakage Discovered on Control Rod Drive Water Filter 3B.Caused by Cracked Drain Line 3-4802B. Repair Procedure Initiated
ML20085J9863 April 1974Ao:On 740325,during Refueling Surveillance,Eight of 16 Area Temp Switches for HPCI Found W/High Operating Points.Cause Not Found.Calibr Kit on Order from Manufacturer
ML20085K04125 January 1974Ao:On 740116,during Electromatic Relief Valve Surveillance, Valve 3-203-3A Failed to Open.Disassembled Valve Revealed That Disc Retainer Installed
ML20085K06020 December 1973Ao:On 731212,w/reactor at Full Temp & Pressure,Mechanical Failure of Oil Line in HPCI Turbine Control Sys Rendered Turbine Operable.Caused by Full Circumferential Sheer Failure of Pipe Bushing.Bushing Replaced
ML20085K07025 January 1974Ao:On 740117,during Operability Test on Hpci,Sys Revealed to Be Inoperable.Caused by Burrs on Cylinder Wall & Piston of Turbine Stop Valve.Burrs Removed & All Parts Thoroughly Cleaned & Inspected
ML20085K08022 January 1974Ao:On 740114,during Routine Monthly Surveillance Testing, Condenser Low Vacuum Scram Switches PSL3-503A,B,C & D Actuated Below Tech Spec Setpoint.Cause Not Stated. Different Type of Switch Will Be Installed
ML20085K11321 December 1973Ao:On 731214,diesel Generator Cooling Water Pump Breaker Tripped,Following Semiannual Maint Insp.Caused by Defective Breaker.Breaker Replaced
ML20085K1296 December 1973Ao:On 731127,cleanup Valve MO-3-1201-2 Failed to Isolate on Reactor Low Water Level Scram.Caused by Tarnished M Coil in Breaker Auxiliary Contacts.Contacts Cleaned
ML20085K15120 November 1973Ao:On 731112,steam Flow Switches 3-2352 & 3-2353 for HPCI Sys Found Out of Calibr.Caused by Setpoint Drift.Switches Reset
ML20085K19119 November 1973Ao:On 731109,during Routine Monthly surveillance,2/3 Core Height Water Level Sensors LITS-263-73A & B Found to Have Setpoints Above Tech Spec.Caused by Setpoint Drift.Switches Reset
ML20085L6539 August 1971Telecopy Ao:On 710805,scram Relay 590-108A Failed to Drop Out When Deenergized.Cause Unknown.Closure Operation Repeated W/Relays Under Observation W/O Recurrence of Incident.Relays Exercized & Normally Operated
ML20085L7985 August 1971Telecopy Ao:On 710805,scram Relay 590-108A Failed to Drop Out When Deenergized.Cause Unknown.Closure Operation Repeated W/Relays Under Observation & Incident Did Not Occur.All Relays Exercized & Operate Normally
ML20090E43220 November 1975AO 50-237/75-52:on 751116,MSIV AO 2-203-1C Closing Time Found Below Tech Spec Section 3.7.D.1.Caused by Out of Adjustment Hydraulic Bleedoff Valve.Bleedoff Valve Readjusted