Semantic search
Jump to navigation
Jump to search
| 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 |
| ML20024E660 | 4 August 1983 | RO 83-18:on 830804,during Maint Insps on Hydraulic Snubbers, Two Small Bore Snubbers Identified as Being Installed on RCS Hot Leg Vent Piping Downstream of Valves RC-V15A & B.Caused by Personnel Error | |
| 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 | |
| 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 | |
| ML20050A543 | 18 March 1982 | Ro:On 820318,water W/Ph of 3.5 Was Discharged from Secondary Waste Water Neutralizing Tank WT-T-1 Into Plant Discharge Effluent Stream.Caused by Accidental Overflow of Approx 2,500 Gallons of Water from Neutralizing Tank | |
| 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 |
| ML20039C633 | 23 December 1981 | RO 81-14:nine Pipe Support & Structural Interfacing Areas Identified Requiring Further Evaluation & Potential Corrective Action.Failure of Pipe Supports Could Damage safety-related Components.Followup Rept Expected in 14 Days | |
| 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 | |
| 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 | |
| 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 | |
| ML19345A974 | 17 November 1980 | RO 80-013/03L-0 Committed to Forwarding Final Valve Testing Evaluation by 801101.Investigation Requires More Time than Anticipated.Requests Extension Until 801219 | |
| ML19337A863 | 23 September 1980 | RO 80-17:determined Insufficient Documentation to Demonstrate That Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C Environmentally Qualified.Redundant Valves Fully Qualified | |
| ML19338F546 | 23 September 1980 | RO 80-17:on 800923,determined That There Is Insufficient Documentation to Demonstrate Environ Qualification of Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C. Cause Not Stated.Corrective Action Will Be Submitted | |
| ML19330C304 | 4 August 1980 | Ro:On 800716,during Radiation Emergency Exercise,Use of Emergency Notification Sys Phone Line Became Uncertain, Making Accurate Info Transfers Questionable.Recommends That Microphone Headset Be Made Available to Allow Mobility | |
| ML19326E206 | 22 July 1980 | RO 80-15/4P:confirming 800722 Telcon,On 800721,river Water Discharge Temp Was More than 3 F Below Inlet River Water Temp for Approx 6-h.Incident Will Be Reviewed to Determine Corrective Action.Review to Be Included in Followup Rept | |
| ML19326E084 | 27 June 1980 | RO 80-12/IP:during Review of Equipment Required by IE Bulletin 79-01B,found That post-accident Pressure & Temp Would Be Higher than Postulated in NSC 730705 Rept.Short & long-term Action to Be Discussed in Followup Rept | |
| ML19323H342 | 6 June 1980 | RO-80-10/1P:on 800603,B&W Ltr Informed Util of Potential Reportability of Steam Generator Tube Rupture Safety Analysis.Caused by Nonconservative Error in Fsar.Corrective Action Will Be Addressed in Followup Rept | |
| ML19323D515 | 23 April 1980 | RO 80-07/TP:on 800423 Results of Radiographic Exams of Piping Welds Associated W/Reactor Bldg Penetrations 415-16 for Leak Rate Test Sys Showed Several Welds Not within Tech Specs.Unit Is Shut Down | |
| ML19309A783 | 26 March 1980 | RO 80-06/1P:on 800325,during Refueling Frequency Reactor Bldg Local Leak Rate Test of Valve RB-V7,updated Total Leakage Exceeded Tech Specs.Testing Is Continuing W/Approx 1/4 of Test Program Complete | |
| ML19322B508 | 8 November 1979 | RO 79-17/1P:on 791108 Support Boltings for Rigid Anchor DHH-127A Found to Be Inadequate in Design & Installation. Details & Corrective Action Will Be Addressed in Followup Rept | |
| 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 | |
| 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 | |
| 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 | |
| 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 | |
| ML19308A524 | 2 February 1978 | RO 78-08/1P:on 780202,util Informed by NSSS of Deviation Discovered Between FSAR Steam Line Break Analysis & Actual Operating Parameters.Procedure Mod Will Limit Secondary Site Water Volume | |
| 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 |