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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20042D840 | 30 March 1990 | Supplement to 900105 Special Rept Re Inoperability of Diesel Fire Pump Due to Failure in Right Angle Gear Drive. Broken Studs Replaced W/Cap Screws Per Vendor Recommendations & Preventive Maint Activity Added | |
| ML20012C686 | 15 March 1990 | Ro:On 900204,daily Functional Test Not Done for Portable Fire Detection Sys.Caused by Shift Supervisor Failure to Ensure That Test Was Done.Requirements of Daily Functional Test Will Be Added to Operations Dept Monthly Activity Log | |
| ML20005F440 | 5 January 1990 | Special Rept:On 891129,diesel Fire Pump Failed While Providing Water to Support Cleaning Activity Unrelated to Fire Protection Sys.Caused by Broken Studs.Broken Studs Replaced W/Cap Screws Per Vendor Current Recommendation | |
| ML20050A965 | 22 March 1982 | RO NP-09-82-02:on 820222,free Chlorine Discharged in Excess of Ets,Section 2.3.1 Limit of 2-h Per Day.Caused by Equipment Deficiency.Feed Rate Will Be Verified During Chlorination Sys Lineup Changes | |
| ML20040G119 | 3 February 1982 | RO NP-09-82-01:on 820104,max Discharge Temp Above Ambient Lake Temp Limit Was Exceeded During Unusual Weather Change. Alarm T189 Setpoint Changed from 15 F to 17 F | |
| ML20010G307 | 31 August 1981 | Ro:Ie Bulletin 80-11 Analysis Determined That Listed Walls Would Be Overstressed During Seismic Event | |
| ML20005B383 | 25 June 1981 | RO NP-09-81-01:on 810526,max Discharge Temp Differential, Above Ambient Lake Temp,Was Slightly Exceeded.Caused by Difficulty in Maintaining Balance Between Operating to Prevent Exceeding Limit & to Prevent Cooling Tower Damage | |
| ML19350C226 | 17 March 1981 | Corrected Page 3 to Supplemental Info for LER 80-090 | |
| ML19341C239 | 18 February 1981 | Forwards Revised Supplemental Info Sheets for LER 79-050 Re Unplanned Reactivity Insertion.Caused by Mechanical, Personnel & Procedural Error.Valve Mu 39 Disassembled & Gaskets Installed | Shutdown Margin |
| ML19340C828 | 1 December 1980 | Supplemental Info Re RO NP-32-80-12:on 800724,w/unit in Mode 5,loss of Decay Heat Flow Observed.No Indication for Valve Position of Decay Heat Isolation Valve DH12.Revision Replaces Supplemental Info for RO 80-058 | |
| ML19345A846 | 18 November 1980 | Ro:On 801117 All Four Containment Pressure Transmitters Found to Be Inoperable Due to Surveillance Test Procedure Error.Emergency Tech Spec Relief Requested | |
| ML19337B428 | 9 September 1980 | RO NP-09-80-01:on 800116 & 0210,discharge Temp for Liquid Effluents Exceeded 20 F Above Lake Temp Due to Procedural Deficiencies.Cooling Tower Was Operated in Bypass Mode Causing Temp to Elevate Above Normal Temp During Startup | |
| ML19331B903 | 4 August 1980 | Ro:On 800803,heat Decay Flow Interrupted.Caused by Traveling Decay Heat Isolation Valve DH11 During Safety Features Actuation Sys Removal.Bistable Reinstalled & Pump Restarted within 3 Minutes | |
| ML19331B900 | 26 July 1980 | Ro:On 800724,decay Heat Flow Interrupted Twice.Caused by Inadvertently Shorted Decay Heat Isolation Valve DH12 Fuse Clip to Ground & by Tripped Output Bistable BA413 During Facility Change Request Work | |
| ML19320B992 | 27 June 1980 | Ro:On 800627,pipe Support HCB-40-41 on Component Cooling Water Supply to Control Rod Drive Mechanism Found Not Installed.Also,Lateral Restraint CCA-8-H15 on Pressurizer Relief Inlet Located 9 Inches from Analyzed Location | Earthquake |
| ML19312E164 | 23 May 1980 | Ro:On 800430,chemistry & Health Physics Individual Received Dose of 4.7 Rems.Cause of Exposure Was Erroneously Low Reading on Meter or Misreading of Teletector.Individual Was Removed from Working in Radiation Controlled Areas | Locked High Radiation Area |
| ML19309G734 | 19 April 1980 | Ro:On 800418,discovered That Level of RCS Had Dropped Significantly.Control Room Operator Tripped Running Decay Heat Pump Because of Concern for Possible Loss of Suction. Caused by Vent Valve in Decay Heat Sys | |
| ML19305C965 | 2 April 1980 | NP-11-80-01,describing 791022 Beach Well Sample Which Indicated Tritium Concentration Three Times Beyond Normal. Procedure Changed to Require Monthly Rather than Quarterly Sampling | |
| ML19294B519 | 15 February 1980 | Ro:Reanalysis of RCS Pipe Restraints Revealed Less Conservative Design than Assumed on Two Reactor Coolant Hot Leg Whip Restraints Near Steam Generator Tops.Cause Unstated.Action During Refueling Outage in Eight Wks | |
| ML19296A926 | 12 February 1980 | RO-NP-09-80-01:on 800116,during Normal Plant Startup,Temp Differential Limit Between Station Liquid Effluent Discharge & Lake Temp Was Exceeded.Caused by Operation of Plant W/ Cooling Tower in Bypass Mode | |
| ML19276H551 | 13 November 1979 | Ro:On 791112,during Seismic Supports Analysis,Safety Factors on 11 Seismic Supports Found Lower than Expected.Unit Was in Cold Shutdown.Caused by Design Error in Initial Stress Calculations.Hangers Will Be Modified | |
| ML19210D703 | 12 November 1979 | Ro:On 791109,steam & Feedwater Rupture Control Sys Steam Generator Low Level Trip Setpoint Discovered Less Conservative than Tech Spec Requirements.Caused by Level Transmitter Setpoint Drift.Design Work Underway | |
| ML19254F926 | 2 November 1979 | RO-NP-09-79-06:on 791008,station Vent Recorder UJR5023 Was Inoperable.Caused by Recorder Not Advancing Paper Under Printer Due to Drive Shaft & Gear Mechanism Jam.All Ujr Recorders Will Be Replaced | |
| ML19275A591 | 27 September 1979 | RO NP-09-79-05:on 790831,during Review of Station Vent Data, Physicist Determined That Vent Recorder Was Inoperable. Caused by Inoperable Computer Point.Recorder Recalibr & Computer Input Card Changed | |
| ML19253A096 | 29 June 1979 | Notification of Violation of Tech Spec 3.4.1 on 790628. During Surveillance Testing on Reactor Protection Sys Channel 4,instrument & Control Technician Shorted Several Terminals W/Allegator Clip | |
| ML19282B705 | 28 February 1979 | Ro:On 790228,during Maint,Startup Transformer 01 Was de- Energized,But Addl Surveillance Required by Action Statement of Tech Spec 3.8.1.1 Was Not Performed.Caused by Personnel Oversight.Surveillance Testing Begun Approx 2-h Later | |
| ML19282A868 | 21 February 1979 | RO NP-09-79-04:on 790126,station Vent Monitor Re 2024 Generated Excessive Noise;Later Pump for Station Vent Monitor Re 2025 Seized.Caused by Normal Vane Wear & Low Flow During Testing.Pumps for Both Monitors Replaced | Grab sample |
| ML19269C595 | 1 February 1979 | RO NP-09-79-02:on 790104,svc Water Sys Header Outflow Radiation Monitor Re 8432 Found Inoperable.Caused by Design Error Resulting in Component Deficiency.Flow Switch on Re 8432 Replaced & Facility Change Request Prepared | Grab sample |
| ML19256A801 | 12 January 1979 | Reportable Occurrence NP-09-78-01:on 781215,during Routine Review of Shift Foreman'S Log,Discovered Svc Water Sys Out Header Radiation Monitor RE8432 Had Been Inoperable.Caused Apparently by Design Error.Facility Change Request Prepared | Grab sample |
| ML19289C368 | 5 January 1979 | Reportable Occurrence NP-09-78-03 on 781209-10:discharge Temp for Station Liquid Effluents Exceeded 20 F Limit Above Lake Temp.Caused in Part by Design Deficiency in Sys Used to Determine Effluent Liquid Discharge Temp | |
| ML19256A786 | 2 January 1979 | to Suppl Info Sheet for LER NP-33-78-120 on 781005.Other Svc Water Valves Associated W/Component Cooling Water Heat Exchangers Were Inspected for Similar Inoperable Conditions.No Problems Noted | Stroke time |
| ML19261B212 | 2 January 1979 | RO NP-09-79-01:on 790102,station Ventilation Radiation Monitors Re 2024 & Re 2025 Found Inoperable.Apparently Caused by Component Failure.Previous Occurrences on 770829 & 771214 Not Reported Due to Personnel Error.Units Repaired | Grab sample |
| ML19263C176 | 15 December 1978 | RO-NP-09-78-01 on 781215:svc Water Sys Out Header Radiation Monitor Was Inoperable.Caused by Component Failure Due to Design Error.Personnel Informed of Environ Tech Specs | Grab sample |
| ML20027A375 | 22 September 1978 | RO NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped Removing One of Two Reactor Coolant Pumps of Loop from Operation.B&C Phase Surge Capacitors Were Discovered to Be Damaged Due to Design Deficiency | |
| ML19329B035 | 18 July 1978 | RO 78-072-04-T-0:on 780710,station Effluent Chlorine Concentration Exceeded Tech Spec Limits.Caused by Personnel Mistakenly Returning Intake Chlorinator to Automatic Return to Svc to Be Expedited | |
| ML19317F531 | 17 April 1978 | Ro:On 780414,taped Electrical Terminations on Containment Air Cooler Units Found Not to Have Required LOCA Qualification.Caused by Mfg Inadequacy.Terminations to Be Reworked W/Qualified Tubing | |
| ML19317F562 | 24 February 1978 | Ro:On 780221,control Rod Drive Sys Trip Circuit Breaker Cabinets Found to Have Inadequate Welds.Welds to Be Lengthened to Conform W/Shaker Table Test During Apr 1978 Outage | |
| ML19317F538 | 16 November 1977 | Ro:On 771110,defect Discovered in Auxiliary Feed Pump Turbine Installed at Facility.Involves Potential for Governing Valve to Close While Turbine Not in Svc.Closure Caused by Excessive Vibration of Adjacent Startup Feed Pump | |
| ML19329A782 | 12 October 1977 | RO NP-33-77-73:on 770917,makeup Pump 1-2 Removed from Svc to Allow Repair of Oil Leak on Outboard Bearing Plate. Caused by Design Deficiency in End Plate Seal.New O-ring Installed | |
| ML19317F535 | 11 October 1977 | Ro:On 770930,defect Discovered in Governor on Auxiliary Feed Pumps Installed at Facility.Potential Created for Failure of Both Auxiliary Feed Pumps to Come Up to Design Speed Upon Startup.Superceded Util 771005 Ltr | |
| ML19329A812 | 4 October 1977 | RO NP-33-77-76:on 770901,reactor Coolant Pump 1-2-1 Tripped.Caused by Low Seal Injection & Component Cooling Water Flow,Due to Personnel Error.Instrument Air Valves Relabeled | |
| ML19329A796 | 4 October 1977 | RO NP-33-77-74:on 770907,decay Heat Suction Valve DH-12 Closed During Switching from Normal to Alternate Power Supply for Valve.Caused by Design Deficiency in Interlock/Control Circuit.Wiring Change in Process | |
| ML19329A807 | 28 September 1977 | RO NP-33-77-75:on 770829,RCS Have Less than 525 F in Mode 2,startup.Caused by Procedure Error in Shutdown Procedure & Fact That Only Three Reactor Coolant Pumps Were in Operation.Reactor Shut Down | Shutdown Margin |
| ML19319B822 | 27 September 1977 | RO NP-33-77-62:on 770825,auxiliary Feed Pump 1-1 Rendered Inoperable During Permanent Pressure Relief Valve Psv 4980 Installation.Relief Valve Installation Completed,Auxiliary Feed Pump Cooling Water Restored & Pump Declared Operable | |
| ML19329B652 | 26 September 1977 | RO NP-09-77-02:on 770830,during Surveillance Test,Personnel Discovered That Weekly Gaseous Grab Sample from Station Vent Monitor Was Not Obtained.Caused by Component Failure. Stack Radiation Monitor Returned to Svc | Grab sample |
| ML19319B815 | 22 September 1977 | RO NP-33-77-59:on 770826,intermediate Range Nuclear Instrument NI-3 Disconnected from Reactor Protection Sys & Connected to Reactimeter to Perform Reactivity Measurements. NI-4 Operable During Test.Power Level Maintained at 5% | |
| ML19319B809 | 22 September 1977 | RO NP-33-77-64:on 770827,reactor Coolant Pump Motor 1-1-2 Tripped W/Instantaneous Ground & Differential Current Relay Indicating Fault.Caused by Damaged B&C Phase Surge Capacitors.Capacitors Repaired & Setpoints Reset | |
| ML19274D939 | 22 September 1977 | LER NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped,Removing One of Two Reactor Coolant Pumps from Operation.Caused by Damage to Surge Capacitors Due to Insufficient Mounting Base | |
| ML19289D517 | 22 September 1977 | Updated RO NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped,Removing Reactor Coolant Pump from Operation.Caused by Damaged Surge Capacitors.Capacitors on All Four Reactor Coolant Pump Motors Replaced W/Units of New Design | |
| ML19319B786 | 19 September 1977 | RO NP-33-77-69:on 770823,hydraulic Snubber EBD-19-H 144 Discovered Upside Down.Caused by Loose Lock Nut on Snubber Extension Piece Allowing Rotation & Placing Fluid Reservoir Below Cylinder.Snubber Purged & Tested.Lock Nut Tightened |