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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20045B064 | 10 June 1993 | Special Rept 93-004:on 930512,fire Rated Assemblies Were Inoperable for More than 14 Days Due to Inadequate Design. LCO 1-93-2010 Initiated,Appropriate Fire Detectors Were Verified Operable & Fire Watch established.W/930610 Ltr | Safe Shutdown Fire Barrier Continuous fire watch Fire Watch Hourly Fire Watch |
| ML20044F610 | 21 May 1993 | Special Rept 2-93-002:on 930430,licensed Plant Operations Declared Fire Door Inoperable.Caused by Fire Door 2L48-2R53 Blocked Open.Fire Door 2L48-2R53 Restored to Operable Status & LCO 2-93-238 Terminated | |
| ML20044D083 | 3 May 1993 | Special Rept 1-93-003:on 930322 & 0405,discovered That Fire Wrap Matl Not Installed on Several safety-related Cable Trays & Trays Not Installed Properly Following Breach on 930301.Maint Work Order Issued to Make Repairs | Safe Shutdown Fire Barrier Continuous fire watch Fire Watch Hourly Fire Watch |
| ML20043A986 | 21 May 1990 | Special Rept 90-002:on 900328,portions of Recirculation Pump Motor Generator Set Room Wall Declared Inoperable.On 900327,electrical Raceways Declared Inoperable Due to Damaged Fire Wrapping.Hourly Fire Watch Initiated | Safe Shutdown Fire Barrier Hourly Fire Watch |
| ML20042F953 | 7 May 1990 | Special Rept 90-003:on 900329,20 Smoke Detectors on Working Floor of Control Bldg Inoperable.Caused by Damaged Power & Control Cables to Detectors Preventing Common Input Signal from Traveling to Computer.Fire Watch Patrol Established | Fire Watch Hourly Fire Watch |
| ML20012E468 | 26 March 1990 | Special Rept 2-90-002:on 900321,seismic Monitoring Instrument Inoperable for Longer than 30 Days.Cause Not Determined.Seismic Instrument Declared Inoperable & Tracking of Limiting Condition for Operation Established | Earthquake |
| ML20005H097 | 16 January 1990 | Special Rept 90-001:on 900109,drywell high-range post-accident Radiation Monitor Inoperable for More than 7 Days.Caused by Monitor Spiking Due to Component Damage. Connector Repaired & Monitor Returned to Svc | |
| ML19327A805 | 10 October 1989 | Special Rept 89-005:on 890919,25,28 & 1002,fire Rated Assemblies Inoperable for Longer than 14 Days.Caused by Fire Rated Assemblies & Sealing Devices Breached to Support Refueling Outage Work Activities.Fire Watches Established | Fire Barrier Continuous fire watch Fire Watch Hourly Fire Watch |
| ML20024E760 | 27 July 1983 | Ro:On 830722,HPCI Auto Initiated & Injected Into Reactor to Restore & Maintain Level Following Loss of Feedwater Transient.Transient Initiated When RFPT 2B Tripped for Unknown Reasons.Rfpt 2A Out of Svc Due to Fire | |
| ML20023C305 | 2 May 1983 | Supplemental Narrative Summary to Rev 5 to RO 50-321/1979-021.Updated Data on Tritium Levels in Groundwater Samples During First Quarter 1983 Encl.No Radionuclides Above Background Identified | |
| ML20028E227 | 11 January 1983 | RO 50-321/1982-04:on 821231,cooling Tower 1A Fire Protection Deluge Sys Tripped,Decreasing Fire Water Storage Tank Vol Below Acceptable Limits.Caused by Failure of Trip Alarm in Cooling Tower.Design Change Requested | |
| ML20052G457 | 30 April 1982 | RO 50-321/1979-021:on 820423,tritium Levels Exceeded 3.0 E4 pCi/1 Allowance for Tritium in Environ Water Samples Per Table 3.2-3 of Ets.Cause Might Be Attributed to Slight Shifts in Main Body of Tritiated Groundwater | |
| ML20052A433 | 6 April 1982 | Ro:On 820217,electrician Found a 125/250-volt Dc Station Svc Batteries W/Low Specific Gravity.When Batteries Placed on Charge,Voltage Went from 130 to 142-volts Dc Causing Topaz Inverter to Trip on High Voltage | |
| ML20052A350 | 26 February 1982 | RO Discussing Substandard Smoke Detection Installation.Mods to Affected Areas & App R Smoke Detection Additions Will Coincide W/App R Schedule to Allow for More Complete Design Review & Consolidated Smoke Detection Plan | Fire Protection Program |
| ML20041A599 | 4 February 1982 | RO 50-321/1979-021,Revision 5.Provides Updated Data on Tritium Levels in Groundwater Samples Taken from Locations Where Average Value Over Fourth Quarter of 1981 Exceeded Samples According to Table 3.2-3 of ETS | |
| ML20010H831 | 22 September 1981 | RO 50-321/1981-090:on 810921,while Performing Surveillance Procedure HNP-1-3414,switches E51-NO12A-D Found to Be Actuating Outside Tech Spec Acceptance Criteria.Caused by Setpoint Drift.Switches Recalibr Per HNP-1-5279 | |
| ML20010H849 | 15 September 1981 | Ro:On 810909,HPCI Injection Valve Would Not Open Automatically During Reactor Level Decrease.Caused by Valve Motor Failure.Valve Opened Manually | |
| ML20010A310 | 30 July 1981 | RO 50-321/1979-021,Revision 5:provides Updated Data on Tritium Levels in Groundwater Samples.Quarterly Average Tritium Levels at Affected Locations Encl | |
| ML20010A002 | 30 July 1981 | RO 50-321/1981-081:on 810729,while Performing Review in Response to IE Bulletin 79-14,Bechtel Engineer Discovered RHR-SW Piping in Vicinity of RHR-SW Strainers Was Inadequately Supported.Caused by Inadequate Design | |
| ML20008F508 | 13 April 1981 | Ro:On 810411,following Reactor Scram on Low Reactor Water Level,Hpci Auto Initiated on Low Reactor Water Level & Injected Into Reactor Vessel.Caused by Loss of Feedwater. Reactor Water Level Was Restored to Normal | |
| ML20008E671 | 26 February 1981 | Special Rept:On 810221,following Reactor Scram on Low Reactor Water Level Due to Loss of Condensate Booster Pump, HPCI Was Manually Initiated & Injected Into Reactor Vessel. HPCI Was Secured After Water Level Was Restored to Normal | |
| ML19351G298 | 12 February 1981 | Ro:On 810113,spray/sprinkler Sys Providing Protection to Hcpi Room Discovered to Be Inoperable for 14 Days.Mod Work & Functional Test Expected to Be Complete Before End of Refueling Outage | Continuous fire watch |
| ML19340E148 | 31 December 1980 | Special Rept 1-sp-80-3:on 801206,during Routine Survey of Waste Oil Drums,Several Areas on Ground Were Found to Be Contaminated.Caused by Storage of Previous Waste Oil Drums. Addl Controls Re Release of Contaminated Oil Under Review | |
| ML19340D825 | 19 December 1980 | Ro:On 801213,sprinkler Sys Providing Protection for Reactor Bldg Heating,Ventilation & Air Conditioning Had Been Inoperative for 14 Days.Caused by Implementation of Design Mods to Bring Sys Into NFPA Code Compliance | |
| ML19347C725 | 19 December 1980 | Ro:On 801213,sprinkler Sys Providing Protection for Reactor Bldg Heating,Ventilation & Air Conditioning Room Had Been Inoperable for 14 Days.Sys Isolated to Implement Mods for Corrective Action to Open Item in IE Rept 50-321/80-02 | |
| ML19340D168 | 4 December 1980 | Ro:On 801031,at 1400-h It Was Determined That Smoke Detectors Were Not Installed Per NFPA Code 72D.Cause Not Stated.Analysis Being Made of All Detection Sys & Design Work for Affected Sys Initiated | |
| ML19338F985 | 21 October 1980 | Ro:On 801009,following Reactor Scram on Low Reactor Water Level Due to Loss of Feedwater,Hpci Tripped on High Reactor Water Level.Caused by HPCI Auto Initiating on Low Reactor Water Level & Injecting Into Reactor | |
| ML19338D482 | 15 September 1980 | Ro:On 800908,following Reactor Scram,Hpci Auto Initiated & Injected Due to Low Reactor Water Level.Caused by MSIV Closure,Which Caused Reactor Scram,Loss of RFPT & Increased Reactor Pressure.Hpci Returned Water Level to Normal | |
| ML19330B547 | 29 July 1980 | Ro:On 800521 & 0711,following Reactor Scram HPCI Auto Initiated & Injected.Hpci Allowed to Return Reactor Level to 58 Inches.Msiv Closed Rendering Reactor Feed Pump Turbine Unavailable for Injection.Hpci Started Manually & Injected | |
| ML19320D454 | 14 July 1980 | Ro:On 800711,Unit 1 LPCI Inverter Tripped & Unit 2 4-kV Bus 2F Supply Breaker & HPCI Tripped.Supply Breaker Trip Caused by Jumper Missing from Neutral Leg.Motor Valve on HPCI Replaced Making It Operable.Events Submitted Per Ieb 80-17 | |
| ML19329F924 | 2 July 1980 | RO 50-321/80-076:while Reviewing as-builts Submitted Per IE Bulletin 79-14,util Discovered Hangers 1E11-RHRH-196 & 1E11-RHRH-313 Would Not Adequately Support Loads During Dbe. Caused by Faulty Design in Incorrect Valve Weights | |
| ML19329F922 | 2 July 1980 | RO 50-366/1980-100:on 800702,while Performing Surveillance Procedures HNP-2-3002 & HNP-2-3172M,high Drywell Pressure Switches 2C71-N002A Through D & 2E11-N011A Through D Found Out of Tolerance.Caused by Setpoint Drift.Switches Recalibr | |
| ML19329F884 | 27 June 1980 | RO 50-321/1980-069:on 800626,following Auto Initiation Signal,Hpci Failed to Inject to Reactor Pressure Vessel Due to Isolating on Steam Line High Dp Isolation Signal.Cause Under Investigation.Reset Isolation & Opened Inboard Valve | |
| ML19326D742 | 25 June 1980 | Ro:On 800522,licensee Reviewed Kinemetrics,Inc 800513 Calibr Rept Re Seismic Instrumentation.Triaxial Time-History Accelerograph 2L51-NO21 Calibr Indicates Excessive Change in Longitudinal Channel Characteristics | |
| ML19329F873 | 23 June 1980 | RO-50-321/1980-61:on 800622,while Preparing to Run RHR Sys, B RHR Loop Min Flow Manual Valves Were Discovered Closed. Caused by Failure to Return to Open Position After Loop Was Taken Out of Shutdown Cooling Mode.Valves Locked Open | |
| ML19318A651 | 12 June 1980 | RO 50-321/1980-062:on 800612,w/facility in Cold Shutdown, Investigation Began to Determine Cause of Pavement Deflection Which Occurred Beneath Crane Outrigger Pad at Intake Structure.Cause of Fill Separation from Pipe Unknown | |
| ML19318A632 | 2 June 1980 | RO 50-321/1980-055:on 800531,snubber 36 on X32-1F7,1-inch Instrument Line from Recirculation a Loop,Appeared Locked Up During Visual Insp.Caused by Snubber Corrosion.Snubbers Failing Surveillance Test Will Be Replaced Prior to Startup | |
| ML19318A649 | 30 May 1980 | RO 50-321/1980-054:on 800530,nondivisional Cables H21-P173-C010 & H21-P173-C013 Found Routed W/Div I & II Type Cables/Raceways.Caused by Design & Installation Error.Design Change Request 80-166 Submitted for Cable Rerouting | |
| ML19318A643 | 27 May 1980 | RO 50-321/1980-053:on 800524,discovered That Loss of Essential Motor Control Ctr 1B(R24-S011) or Loss of Diesel Generator 1A During Loss of Offsite Power Will Cause RHR & Core Spray a Loops to Be Inoperable.Caused by Faulty Valve | |
| ML19323E310 | 30 April 1980 | Supplemental Narrative Summary to RO 50-321/79-021,Revision 5:updates Tritium Levels in Ground Water Samples.Any Releases to Unrestricted Areas Are Miniscule & Result in Insignificant Doses to Public | |
| ML19309G044 | 24 April 1980 | Ro:On 800206,HPCI Was Manually Started & Injected Into Reactor Vessel to Maintain Reactor Vessel Water Inventory Following Trip of Reactor Feed Pump.Caused by Loss of Reactor Feed Pump Loop Seal.Hpci Was Shut Down | Loop seal |
| ML19309F135 | 7 April 1980 | RO 50-366/1980-045:on 800405,during Cold Shutdown,Leak Rate Test on Automatic Depressurization Sys Valve Air Supply Accumulator Check Valves Indicated Unacceptable Leakage Rates.Cause Under Investigation.No Immediate Action Taken | |
| ML19290E631 | 3 March 1980 | Suppl to RO 50-321/1979-021,Revision 5 Providing Data on Tritium Levels in Ground Water | |
| ML19296D171 | 18 February 1980 | Supplemental Narrative Summary to RO 50-321/1979-021, Revision 5:on 791202,tritium Levels in Groundwater Samples Exceeded Limits.Caused by Leakage from Blown Seal on Condensate Transfer Pump.Pumps Temporarily Confined | |
| ML19210F030 | 6 November 1979 | RO-79-089:on 791106,while Evaluating as-built Seismic Piping & Supports,Head Vent Line Portion of RHR Head Spray Piping & Bypass to Condenser Valve Chest Found Unsupported.Caused by Omission of Supports from Design | |
| ML19209C651 | 11 October 1979 | RO 50-366/79-112:on 791011,during Shutdown for Maint,Found That Intermediate Range Monitor Had Been Removed & Was Not in Control Rod Driveline Cavity of Drywell.Caused by Removal for Clean Up Operation | |
| ML19249E102 | 11 September 1979 | RO 50-321/1979-OB1:on 790910,LOCA Conditions Discovered Capable of Causing Several Primary Containment & Inserting Valves to Overtravel During Closure.Caused by Differential Pressure Across Valves & Loss of Seating Ability | Overtravel |
| ML19249C891 | 10 September 1979 | Ro:On 790908,Unit 1 Was in Run Position & Unit 2 Was in Hot shutdown,E11-C001A,B & D Pumps Failed to Meet Operability Procedure HNP-1-3167 Due to Formula Errors in Pump Discharge Pressure Calculations.Units Shut Down & Formulas Reviewed | |
| ML19249C879 | 4 September 1979 | RO-50-366/79-98:on 790902,NSSS Supplier Contacted Plant Mgt About Possible Cable Separation Irregularities within HPCI Sys.Caused by Design Error.Proposed Design Change in Process | |
| ML19249C906 | 29 August 1979 | Ro:On 790812,RHR Pump Suction Torus Isolation Valve E11-F004B Leaked Back Toward Containment.Local Leak Rate Test Performed.Leakage Less than Acceptance Criteria. LER Not Required.Valve Tightened & Tested Satisfactorily |