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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20046C366 | 5 August 1993 | Special Rept:On 930629,seven Blockout Type Penetration Fire Barriers & on 930713,six Sleeve Type Penetration Fire Barriers Determined to Be Nonfunctional.Repairs Completed & Fire Barriers Restored to Functional Status | Fire Barrier Fire Watch |
| ML20044H365 | 1 June 1993 | Special Rept:On 930427,EDG Failed to Auto Start During Performance of Main Dam Auxiliary Power Diesel Periodic Test.Corroded Wires & Lugs Appeared to Be Loose.Control Wire Connections Cleaned & Aged Wires Replaced | |
| ML20024H647 | 31 May 1991 | Special Rept:On 910227,svc Water MOVs Associated W/ Recirculation Spray Heat Exchangers Exceeded Torgue Limits & Stopped in Mid Position While Being Opened During Test.Event Reported on Voluntary Basis to Provide Info to NRC | |
| ML20005E160 | 22 December 1989 | Special Rept:On 891218,heat Trace Sys for Kaman Vent Stack a Radiation Monitor RI-VG-179 Declared Inoperable.Sys Removed from Svc & Tech Spec 3.3.3.1 Action Statememt Entered.Sys Will Be Repaired & Returned to Svc by 900130 | |
| ML19332G047 | 11 December 1989 | Special Rept:On 891202,Kaman Process Vent Radiation Monitor Exceeded Action Statement of Tech Spec 3.3.3.1 Since Monitor Not Returned to Operable Status within 7 Days.On 891125, Monitor Alarmed in Control Room Every 15 to 30 Minutes | |
| ML20023D218 | 10 May 1983 | Ro:On 830509,w/unit at 100% Power,Severe Hydrogen Leak Discovered on Hydrogen inner-cooled Turbine Generator.Unit Rampdown Ordered & Hydrogen Vented to Atmosphere.Emergency Terminated When Pressure Reached Less than 10 Psig | |
| ML20009F975 | 26 March 1981 | Ro:On 810325,station Personnel Discharged 22,000 Gallons of Condensate Water Over 14-h Period.Samples Taken at Beginning & End of Discharge.Results Listed | |
| ML19329F881 | 11 July 1980 | RO 80-55/O1T-0:during Review of FSAR Safety Analyses for Boron Dilution Accident Potential,Nonconservatism in Cold Shutdown Analysis Determined.Cause Unknown.Accident Analysis Review Initiated | |
| ML19329F970 | 27 June 1980 | RO-80-029/01T-0:on 800627,pressurizer Power Operated Relief Valve PCV-2456 Inadvertently Opened in Mode 3 Following Valve Maint Activities.Corrective Action Will Be Taken Pending Completion of Investigation | |
| ML18139A299 | 6 June 1980 | Ro:Several Lines in Low Head & High Safety Injection Sys Were Not Analyzed for Effects of Fluid Temp Below 70 F. Review of New Nozzle Loads Showed Load on Pump Exceeded Vendor Allowable Load.Multiphase Program Proposed | |
| ML19312E590 | 5 June 1980 | RO 80-10/01T-0:on 800605,during Review of ECCS Piping, Loading on Low Head Safety Injection Pump Nozzles Was Discovered to Exceed Design Stress Allowable.Caused by Deficiency in Piping Sys Stress Analysis | |
| ML19290C683 | 4 February 1980 | RO 80-02/01T-0:during Review Required by IE Bulletin 79-14, Stress Discovered Over Design Allowable on Pipe Hangers & Snubbers.Caused by Incorrect Valve Weights Used in Design Calculations.Hangers & Snubbers Will Be Modified | |
| ML19270K264 | 25 January 1980 | RO-80-19:on 800124,during Equipment Qualification Review for IE Bulletin 79-01,qualification Discrepancy Discovered in Svc Water Radiation Pumps for Recirculation Spray Heat Exchangers.Cause Unknown | |
| ML19290C684 | 21 January 1980 | RO-80-01/01T-0:on 800121,excess Letdown Lines Had Several Pipe Stress Points Above Normal or Upset Allowables.Caused by Incorrect Use of Valve Weight for HCV-1201 Pipe Stress Calculations.Snubber Will Be Added to Line | |
| ML19270H794 | 14 December 1979 | Followup Suppl to Ler/Ro 79-15.Higher Pipe Stress Code Allowable Should Have Been Used by Teledyne.Pipe Stress on Kubes 1.5 inches-RC-105-1502-01 Not Over Code Allowable | |
| ML19257A345 | 12 December 1979 | RO 79-158/01T-0:during Review Required by IE Circular 78-08, S&W Discovered Pressure Differential Switches PDS-HV1228A & B Not Seismically Qualified.Cause Unknown.Problem Being Reviewed | |
| ML19257A343 | 12 December 1979 | RO 79-157/01T-0:during Review of Seismic Analyses Per IE Bulletin 79-14,nonconformance in Pipe Support Design Was Discovered by S&W.Caused by Incorrect Valve Weights Used in Support Calculations | |
| ML19268C171 | 27 November 1979 | Supplements RO 79-141/01T-0:while Reviewing Operation of Secondary Ventilation Sys,Sys Discovered to Operate in Manner Not in Keeping W/Accident Analyses.Cause Unknown. Matter Under Review | |
| ML19268C170 | 19 November 1979 | Supplements RO 79-141/1T-0:on 791114,determined,upon Review of Fsar,That Previously Reported Deficiency Re Nonautomatic Restart of Casing Cooling Pumps on Restoration of Onsite Emergency Power Is Not Deficiency | |
| ML19268C174 | 19 November 1979 | Followup to RO 79-152/01T-0:on 791118,Westinghouse Notified Util of Potential Reduction in Conservatism Re Error Allowances Assumed in Analysis for Power Range Neutron Flux High Negative Rate.Setpoints Will Be Changed | |
| ML19268C172 | 16 November 1979 | Supplements RO 79-141/01T-0:while Reviewing Operation, Recirculation Cooling Fans & Control Rod Drive Fans Found to Operate in Manner Not in Keeping W/Accident Analyses. Cause Unknown.Problem Being Reviewed by Engineering Svcs | |
| ML19268C173 | 14 November 1979 | Supplements RO 79-141/01T-0:while Reviewing Operation of Svc Water Sys,Casting Cooling Subsys & Recirculation Spray Sys, Sys Found to Operate Not in Keeping W/Accident Analyses. Cause Unknown.Discrepancies Under Review | |
| ML19308B113 | 14 November 1979 | Submits 24-h Reportable Event Written Followup Re Undetecable Failure of P-4 Contacts in Engineered Safety Features Actuation Sys.Caused by Westinghouse Design Error. Procedures for Testing P-4 Contacts Being Evaluated | |
| ML19268C169 | 6 November 1979 | RO-79-151/01T-0:during Review of Valve Weights in Conjunction W/Ie Bulletin 79-14,discovered That Incorrect Seismic Response Spectrum Was Used in Pipe Stress Analysis. Cause Not Known.Investigation in Progress | |
| ML19254F270 | 18 October 1979 | RO 79-142/01T-0:on 791018,during Pressurization of Steam Generator C,Channel IV Pressure Indications for Generators a & C Observed to Be Swapped.Caused by Piping Being Connected to Wrong Transmitters.Piping Will Be Changed | |
| ML19249E114 | 14 September 1979 | Ro:On 790914,ambient Temp Ranges Could Have Existed in Excess of Capability of Diesel Generator Fan Cooling Sys. Caused by Fan Blades Not Having Proper Pitch Setting to Provide Necessary Cooling at All Temps.Evaluation Underway | |
| ML19249E100 | 12 September 1979 | RO on 790912:while Performing Evaluation to Determine When to Secure Quench Spray Pumps After Loca,Error Discovered in Emergency Procedure 1-EP-2 Requiring Pumps Be Secured at Level of 28.1%.Error Corrected;Cause to Be Determined | |
| ML19208C432 | 12 September 1979 | Ro:On 790912,noted That Station Curve for Refueling Water Tank Was Incorrect,Resulting in Tech Spec Upper Tank Level Limit Being Exceeded.Cause Unknown.Tank Level Lowered.Change to Station Curve Being Drafted | Coast down |
| ML19242A665 | 26 July 1979 | RO 79-091/01T-0 on 790725:followup Rept on Discovery That Component W-104 Dual Peripheral Driver in 7,300 Series Signal Comparator Cartds Could Fail,Causing Associated Bistable to Fail in Unsafe Mode | |
| ML19225C947 | 23 July 1979 | RO 79-089/01T:discovered Possiblity of Failure of Process Cards,Causing Adverse Effects on Associated Loop Actions. Process Card Failure Analysis Performed | |
| ML19270G653 | 25 April 1979 | RO 79-057/01T-0 on 790424:potential Overload exists;4,160 Volt Transfer Bus & Feeder Breakers Are Not Capable of Continually Carrying Full Load Current.Caused by Improper Sizing of Transfer Bus Equipment | |
| ML19263C959 | 5 February 1979 | Telcon Rept:Util Informed Region 2 of Potential Hydraulic Transient (Water Hammer) in Recirculation Spray Coolers During Operation in Post LOCA Environ.Magnitude of Transient & Applicability to Unit 1 Have Not Been Determined | |
| ML19294A528 | 14 November 1978 | RO 78-100 on 780803:rept Submitted Re Deficiency in Seismic Analysis of Reactor Vessel Insulation.Mod Made,But Was Not Seismically Analyzed |