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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20042E226 | 9 April 1990 | Special Rept:On 900227,fire Protection Alarm Reporting Sys Inoperable for More than 14 Days.Compensatory Fire Watches Instituted in Affected Areas & Failure & Malfunction Rept 90-44 Written to Document Problem | Fire Watch |
| ML19325E902 | 6 November 1989 | Special Rept:On 890929,fire Water Supply Sys Storage Tanks Declared Inoperable.Caused by Drained Storage Tank. Fwst (T-107A) Refilled & Declared Operable on 891007 | |
| ML20052E180 | 27 April 1982 | RO 82-011/01X-0:on 820427,review of Water Level Anomaly, Determined That Facility Entered Limiting Condition for Operation W/O Insertion of Control Rods.Special Order 82-04 Will Be Issued 820428 to Prevent Recurrence | Half scram |
| ML20050D585 | 1 April 1982 | Ro 82-008/01x-0:on 820331,HPCI Sys Declared Inoperable Due to Failure of HPCI Injection Valve Mo 2301-8 to Go Full Open During Performance of Surveillance Test 8.I.13. Cause Not Stated.Priority a Maint Request Issued | |
| ML20042A458 | 9 March 1982 | Telecopy RO 82-006/01X-0:on 820309,HPCI Stop Valve Main Disc Flange Which Should Be Attached to Main Disc by Four Cap Screws Found W/Three Cap Screws Broken.Cause Not Stated. Engineering Support Requested | |
| ML20039E077 | 15 December 1981 | RO 81-1:on 811208,util Received Analysis Rept from Yankee Atomic Environ Lab Indicating Potentially Reportable Concentration of Co-60 in Irish Moss Sample from Indicator Station.Calculated Doses Not Considered Significant | |
| ML20050C212 | 25 March 1981 | RO 82-07/01X-0:on 810325,HPCI,reactor Core Isolation Cooling & Reactor Water Cleanup Pipe Excess Flow Isolation Setpoints Set Unconservatively.Caused by Exclusion of plant-specific Parameters from Original Calculation | |
| ML20049A336 | 14 November 1980 | RO 80-084/01X-0:on 801113,during Repairs to D Msn Discovered Water Leaking from 2 Inch Vessel Drain Line Which Connects to Rwcv Sys.Caused by Defective 2 Inch Pipe Coupling Weld. Leak Isolated & Coupling Rewelded | |
| ML19340B161 | 15 October 1980 | RO 80-072/01X-0:on 801014,during Steady State Operation,Mgt Review Revealed That Reactor Protection Sys Trip Level Setting Was Miscalibrated to Nonconservative Level.Caused by Calculation Error.Monitors Were Immediately Recalibrated | |
| ML19340B162 | 14 October 1980 | RO 80-070/01X-0:on 801010,during Steady State operation,480 Volt Breaker B204 Tripped Twice within 10 Minutes, de-energizing 480 Volt Bus B14.Cause Unknown.Bus B14 Was Immediately Returned to Svc by Closing Breaker B204 | |
| ML19351D675 | 3 October 1980 | RO 80-067/01X-0:on 801002,NRC Was Notified That Analytical Reanalysis of RHR Sys B Indicated That as-built Configuration Would Not Remain Functional During Sse.Caused by Design Error.Seismic Anchor Is Being Modified | Safe Shutdown Earthquake |
| ML19343A419 | 11 September 1980 | RO 80-050/01X-0:on 800907,during Surveillance Testing,Diesel Generator Removed from Svc When RBCCW Pump P202D Found Inoperable.Caused by Ambiguous Tech Specs.Tech Specs Will Be Revised to Clarify Limiting Condition of Operation | Safe Shutdown |
| ML19338C428 | 7 August 1980 | RO 80-036/01X-0:on 800807,found Hourly Fire Check of Auxiliary Offgas Bldg Was Not Performed on Continuous Basis After 800707.Hourly Fire Check Reinitiated,Surveillance Testing Completed & Sys Returned to Svc | Fire Watch Hourly Fire Watch |
| ML19330C512 | 17 July 1980 | RO 80-29/01X-0:on 800701,during Surveillance Testing to Verify Operability of Oxygen Analyzer Isolation Valves, SV-5065-23 Failed to Meet Acceptance Criteria for Closing Time,Impacting on Operability of Panel C-19 | Pressure boundary leak |
| ML19309G663 | 8 March 1980 | RO 80-008/01X-0:on 800308,two Irradiated Fuel Assemblies Relocated in Spent Fuel Pool,W/Diesel Generators Inoperable & Secondary Containment Not Intact.Caused by Lack of Knowledge Re Core Drilling for Mods.Fuel Movements Stopped | |
| ML19260D402 | 1 February 1980 | LER 80-004/012-0:during Visual Examination of Core Spray Sparger,Seven Linear Indications Were Recorded.Cause Unstated.Analysis Initiated | |
| ML19257C656 | 24 January 1980 | RO 80-002/01X-0:during Investigation Following Review of IE Info Notice 79-32,several 125-volt Dc Automatic Depressurization Sys Supply Cables Found Routed in Cable Trays Containing HPCI Control Cables.Problem Being Resolved | |
| ML19257C647 | 23 January 1980 | RO 80-001/01X-0:fire Hazards Rept Indicated That Fire in Raceways of Facility Cannot Be Tolerated Because Safe Shutdown Would Be Jeopardized.Cause Unstated.Fire Protection Measures Proposed or Being Completed | Safe Shutdown |
| ML19262B569 | 24 December 1979 | RO-79-048 on 791224:backup Battery Charger,In Use Due to Main Battery Charger 791223 Failure,Tripped & Could Not Be Reset.Cause Under Investigation.Spare Battery Charger Will Be in Svc by 791224 | |
| ML19270H627 | 20 December 1979 | Ro:On 791211,while Transferring Fuel Assembly LTL-656,crane Lifted Assembly Out of Spent Fuel Pool.Caused by Failure to Monitor Hook While Withdrawing from Pool.Assembly Returned to Proper Position | |
| ML19322C024 | 17 December 1979 | RO 79-01/OR:on 791217,while Lowering New Fuel Assembly Into Fuel Pool,Rice Hook Holding Assembly Failed,Resulting in Assembly Falling Onto Spent Fuel.Cause Not Yet Determined. Investigation Underway Re Recovery of Assembly | |
| ML19254C727 | 10 October 1979 | Ro:On 791009,Bechtel Notified Util That Reanalysis of Reactor Bldg Component Cooling Water Sys as-built Configuration Indicated Sys Would Not Remain Functional During Sse.Caused by Design Error.Mods Underway | |
| ML19209B697 | 2 October 1979 | RO 79-036/01X-0:on 791001,util Was Informed That Portion of Loop Piping Does Not Meet SSE Criteria.Caused by Failure to Include Pipe Flange Weights in Design Calculations | Safe Shutdown Earthquake |
| ML19249B573 | 28 August 1979 | RO 79-032/01X-0 on 790828:during Evaluation Performed Per IE Bulletin 79-01,dry Well Sump Containment Isolation Valves AO-7011A & B & AO-7017A & B Were Found Unqualified for Svc. Caused by High Radiation Exposure to Solenoid Valve | |
| ML19249B578 | 28 August 1979 | RO 79-033/01X-0:on 790828,lightning Struck Station Switchyard,Causing Loss of Offsite Power & Reactor Scram. Offsite Power Restored & Reactor Startup Initiated | |
| ML19242C776 | 27 July 1979 | RO 79-027/01X-0 on 790727:lightning Struck Station Switchyard,Causing Loss of Offsite Power & Reactor Scram. HPCI Was Started for Injecting Water Into Vessel.Relief Valve 203-3A Will Be Replaced & Tested Prior to Restart |