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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20042F354 | 30 April 1990 | Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation | Temporary Modification Operability Determination |
| ML20024C127 | 1 July 1983 | Ro:On 830623,visual Insp Revealed Three Broken Holddown Springs.Investigation Incomplete.Ro 269/83-13 Will Be Submitted by 830721 | |
| ML20024C418 | 1 July 1983 | Ro:On 830525,fire Barrier Penetrations Found Nonfunctional. Caused by Design Deficiency.Fire Watch Posted,Penetrations Repaired & Procedures Revised | Fire Barrier Fire Watch Hourly Fire Watch |
| ML20024C414 | 29 June 1983 | Ro:On 830509 & 12,fire Barrier Smoke Exhaust Penetrations 3-K-5-2,3-C-5-3 & 4 Found W/O Seal & 3-C-5-3 Did Not Have Fusible Damper,Respectively.Caused by Inadequate Info & Insufficient Guidance Provided by Design Engineering | Fire Barrier Fire Watch Hourly Fire Watch |
| ML20023B651 | 29 April 1983 | ROs 269/83-10 & 287/83-04 Re 821212 & 830303 Loss of Containment Integrity.Mgt Audit in Progress.Summary List of Completed & Remaining Activities,W/Projected Completion Dates,Encl | |
| ML20028F393 | 19 January 1983 | Ro:On 821220,reactor Trip Circuit Breaker a Failed to Trip When Trip Signal Initiated.Caused by Sticking Undervoltage Relay.Relay Replaced.Contacts Cleaned | |
| ML20027B858 | 21 September 1982 | Ro:Advising That 820820 Occurrence Involving Loss of Electric Power to Valve CCW-8 Determined Not Reportable. Operability of Valve Demonstrated.No Further Action Required | |
| ML20027B769 | 16 September 1982 | RO 269/82-14:investigation Re Reactor Bldg Penetrations That May Not Have Been Leak Rate Tested Incomplete.Rept to Be Submitted by 820930 | |
| ML20052A329 | 9 April 1982 | Informs That Review Per RO-269/82-07 Has Determined That Plant Design & Const Predate Std Re Westinghouse SAI-1 Type Relays Not Meeting Full Surge Requirements | |
| ML20052A426 | 2 April 1982 | RO 269/82-06:on 820306,steam Generator 1B Indicated Tube Leak of 0.08 Gpm.Incident Under Investigation.Next Rept Expected by 820416 | |
| ML20050A975 | 12 March 1982 | RO 287/82-04:on 820226,3A2 HPI Normal Makeup Nozzle Found to Have Broken Thermal Sleeve Tack Welds.Investigation Revealed Cracks in Safe End & Upstream Piping.Next Rept Expected by 820409 | |
| ML20049J554 | 25 February 1982 | Ro:Advising of Delay Until 820311 to Provide Complete Rept of RO-281/82-03 Re Steam Generator Tube Leak | |
| ML20040F761 | 5 February 1982 | Ro:On 820122,during Visual Insp of Core Barrel Assembly, Thermal Shield & Shock Pad Bolts Found Broken & Shock Pad Was Skewed.Thermal Shock Bolts to Be Replaced.Loosened Shock Pad Evaluation Underway | |
| ML20040E687 | 28 January 1982 | RO 269/81-50:on 811229,reactor Bldg Cooling Unit C Declared Inoperable Due to Inability to Open Discharge Valve 1LPSW-24.Investigation & Rept Expected to Be Completed by 820211 | |
| ML20040C842 | 8 January 1982 | Suppl 3 to RO 269/81-11:re Broken Lower Thermal Shield Bolts.Caused by Intergranular Stress Corrosion Cracking in Region of Pronounced Microstructure Transition at head-to-shank Fillet.Bolts Replaced.Drawings Encl | Stress corrosion cracking |
| ML20039F608 | 28 December 1981 | Ro:On 811228,review of Info Re Reactor Vessel Matl Surveillance Program Revealed Calculational Error in Analyses Used to Update Heatup & Cooldown Curves.Unrevised Tech Spec Figures 3.1-1 & 3.1-2 Remain Conservative | |
| ML20038B500 | 3 December 1981 | Ro:On 811201,pressurizer Block Valves Found to Not Meet Design Specs of Closing Against Design Pressure.Caused by Undersized Motor Operator Which Will Not Develop Sufficient Torque to Shut Block Valve | |
| ML20038C796 | 2 December 1981 | Ro:On 811201,discovered Pressurizer Block Valves Did Not Meet Design Spec in That They May Not Close Against Design Pressure.Caused by Undersized Limitorque Operator Model SMB-000-5 | |
| ML20011A723 | 21 October 1981 | Ro:On 811019,four Liquid Waste Releases Were Made W/O Adequate Sampling.Caused by Failure to Make Change to Sample Point.Procedure Revised to Specify Correct Sampling Point for Sys Configuration | |
| ML20010F679 | 4 September 1981 | RO 270/81-14:on 810821,2A1 Reactor Coolant Pump Electrical Penetration Was Discovered Depressurized & Could Not Be Repressurized w/SF6 Gas.Cause Not Stated.Investigation & Complete Rept Will Be Sent by 810918 | |
| ML20038C817 | 25 August 1981 | Ro:On 810814,tritium Concentrations in Downstream Water Samples Exceeded Tech Spec Control Level for Second Quarter of 1981.Analysis of Max Dose Estimates Concluded That Concentrations Will Not Adversely Affect Public Health | |
| ML20010A872 | 5 August 1981 | RO 269/81-11,Suppl 1:on 810715,core Barrel Assembly Thermal Shield Bolts Found Broken.Cause Not Stated.Search for Loose Parts Turned Up All Missing Thermal Shield Parts Except for One Thermal Shield Bolt Head.Investigation Continuing | |
| ML20009H689 | 30 July 1981 | Nonroutine 30-day Rept:On 810623,fire Door 5 Opened to Relieve Excessive Heat from Auxiliary Feedwater Pump Room. Heat Caused by Backleakage Combined W/Hot Temp & Lack of Ventilation.Repairs Scheduled for Fall Refueling Outage | Fire Barrier |
| ML20009E735 | 28 July 1981 | Ro:On 810717,fire Suppression Water Sys Found Inoperable. Caused by Open Main Control Source Breakers.Breakers Closed & Sys Successfully Tested | |
| ML20009H577 | 22 July 1981 | Ro:On 810608,fire Barrier Penetration Fire Seals Found in Nonconformance W/Approved Configuration Requirements. Deficiencies Occurred During Mod 445-N Implementation.Seals Will Be Repaired During Refueling Outage | Safe Shutdown Fire Barrier |
| ML20038C803 | 6 July 1981 | Ro:On 810210,radioactivity Levels of Aquatic Vegetation Samples Exceeded Control Level by Greater than 50 Times.Info Supersedes 810225 Submittal | |
| ML20009F431 | 1 July 1981 | Ro:On 810630,during Performance of Normal Power Procedure, Backup Function of Units Isolating & Transfer Diodes on 125 Volt Dc Instrumentation & Control Sys Was Observed. Proposed Tech Spec Change Will Be Submitted | |
| ML20009H270 | 1 April 1981 | RO:810319 Determination Declaring Portions of Low Power Injection Sys Seismically Inoperable Was Premature.Hanger Noncomformance Repaired within 48-h Per IE Bulletin 79-14. Item Not Reportable Per Tech Spec 6.6.2.1a(9) | |
| ML20005A877 | 25 February 1981 | Ro:On 810219 Analytical Results of Aquatic Vegetation Samples Collected on 810210 Indicated That Radioactivity Levels Exceeded Tech Specs.Cause Not Stated | |
| ML19341B274 | 15 January 1981 | Ro:On 810114,both Channels of Heat Trace for Both Boric Acid Transfer Pumps Determined Inoperable in Violation of Tech Spec 3.2.3.C.Caused by Misleading Step in Procedure for Taking Pump Out of Svc | Boric Acid |
| ML18004B987 | 30 August 1979 | Ro:On 790829,svc Water Booster Pump a Tripped When Svc Water Booster Pump B Was Stopped,In Violation of Tech Specs 3.3.4.1.a.Power Reduction Initiated & Svc Water Booster Pumps Returned to Svc | |
| ML19282D029 | 15 January 1979 | RO 269/7827 on 781214:on 781213,reactor Coolant Temp Became Erratic.Feedwater Problem Resulted from Operation of One or More Feedwater Valves.Power Cords Have Been Fitted | |
| ML19263C984 | 30 November 1978 | RO 270/78-12 on 781105:stop Check Valve from 2AHPI Pump to 2A12C Pump Closed During Flow Test.Valve Was Opened & Check Valve Functional Test Completed | |
| ML19316A370 | 5 June 1978 | RO 269/78-13:on 780427,primary-to-secondary Leak in 1B Steam Generator Occurred.Caused by Tube Leaks.Tube 69-1 Had Weld Crack.Tube 74-2 Had Circumferential Crack.Cracked & Suspect Tubes explosive-plugged.Investigation Continuing | Hydrostatic |
| ML19312C236 | 21 April 1978 | RO-269/78-07 & 09:on 780314 & 22,field Flashing Breaker Found Inoperable.Cause for Repeated Inoperability Has Not Been Determined.Faulty Relays Replaced Before 780322 Failure.Recorder Will Be Installed to Monitor Trip Circuits | |
| ML19316A381 | 11 April 1978 | RO 269/78-08:on 780315,valve FDW-108 Failed to Close.Failure Has Occurred Previously.Caused by Apparent Unsuitability of Valves for long-term Operation in Sys Environ.Valve Stem Lubricated.Valves Will Be Replaced | |
| ML19316A389 | 7 April 1978 | RO 269/78-10:on 780323,Unit 2 Not Verified Operable within Time Limit.Caused by Personnel Error.Station Procedure, Removal & Restoration of Equipment, Not Properly Used. Personnel Instructed by Operating Engineer | |
| ML19316A404 | 7 April 1978 | RO 269/78-06:on 780310,field Flashing Breaker Failed to Close During Startup of Keowee Hydro Unit 2.Breakers & Associated Relays Checked.Circuits Checked.Cause of Breaker Malfunction Unknown.Search for Possible Causes Continues | |
| ML19308A753 | 23 March 1978 | RO 269/78-03:on 780222,Unit 2 Field Flashing Breaker Failed to Close.Cause of Breaker Malfunction Not Determined.Relays in Breaker Control Circuit Were Replaced.Investigation to Control Breaker Sys Faults Continues | |
| ML19316A464 | 15 March 1978 | RO 269/78-04:on 780301,two Reactor Bldg Cooling Units Found Inoperable Simultaneously.Caused by Insufficient Installation Procedures Allowing Trip Point to Be Set Too Low.Breaker Reset & Trip Setpoint Increased | |
| ML19316A417 | 3 February 1978 | RO 269/78-01:on 780203,field Flashing Breaker Failed to Close.Controls Checked & Found in Proper Condition.Breaker Checked & Cleaned.Cause of Failure Not Determined | |
| ML19317F346 | 2 February 1978 | RO 270/78-04:on 780202,nuclear Instruments Found Out of Calibr in Less Conservative Direction & Could Have Prevented Fulfillment of Functional Requirements of Reactor Protective Sys.Cause Not Stated.Administrative Measures Taken | |
| ML19308A797 | 31 January 1978 | RO 269/78-02:on 780105,Keowee Hydro Unit 1 Not Verified Operable within 1-h of Taking Keowee Unit 2 Out of Svc. Caused by Failure to Follow Established Procedures by Personnel.Operators Instructed in Tech Specs | |
| ML19317E045 | 26 January 1978 | RO 269/77-31:on 771229,leakage of Less than 1 Gallon Per Minute Noted.Caused by Failure of Switch 1PS-364 Diaphragm. Switch 1PS-364 to Be Replaced During Future outage.1PT-21P Switch Recalibr & Returned to Svc | |
| ML19316A484 | 19 January 1978 | RO 269/77-30:on 771220,primary Leak Through Pressurizer Spray Bypass Valve RC-2 Indicated.Caused by Packing Leak on Pressurizer Spray Bypass Valve.Valve RC-2 Repacked & Tested for Leaks | Packing leak Unidentified leakage |
| ML19317D963 | 18 January 1978 | Incident Investigation Rept RO-B-692:on 780117,Keowee Unit 2 Removed from Svc for Maint & Keowee Unit 1 Not Verified Operable within 1-h Per Tech Specs.Keowee Unit 1 Verified Operable Upon Discovery | |
| ML19308A784 | 18 January 1978 | RO 269/77-29:on 771219,Keowee Hydro Unit 2 Failed to Start on Initiation from Oconee Control Room.Field Flashing Breaker Failed to Close.Cause Not Determined.Breaker Inspected & Serviced & Found Operable | |
| ML19317D959 | 13 January 1978 | Incident Investigation Rept RO-B-690:on 780113,indications Reading High During Calibr on a Core Flood Tank (IP/0/A/020/01A).Error May Have Allowed Unit Operation in Violation of Tech Specs 3.3.3 | |
| ML19317D878 | 19 December 1977 | RO 269/77-28:on 771216,B&W Discovered Min Vol & Concentration Requirements Were Insufficient for Reactor Shutdown.Cause Not Given.Boron Solution Vol Increased to Provide Adequate Margin for Shutdown | |
| ML19308B170 | 15 December 1977 | RO 269/77-27:on 771215,B&W Discovered Error in Computer Used for Incore Detector Signal Processing.Initial Action to Reduce Positive Imbalance Trip Setpoints by 2.5% |