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| Issue date | Title | Topic | |
|---|---|---|---|
| ML18153B135 | 3 November 1994 | Ro:On 941028,total Suspended Solids Concentration in Spoil Discharge Reached 820 Mg/L.Permit Limitations Expressed as Values Exceeding Ambient Levels | |
| ML18153B411 | 15 December 1993 | Ro:On 931215,discovered Fault in Control Rod Drive Sys, Rendering Control Rod Assemblies in Shutdown Bank a Immovable W/Group 2 at 222 Steps & Group 1 Rods of Control Banks a & C Immovable by Faulted Conditions | Shutdown Margin Enforcement Discretion |
| ML18153D131 | 15 September 1992 | Update to 920703 Special Rept Re Operational Difficulties W/ Waste Gas Decay Tank Hydrogen Monitors.Operability Intermittent & Reliability Not Yet Achieved.Ts Change to Delete Requirement to Monitor Hydrogen Sent on 920628 | Grab sample |
| ML18153D056 | 3 July 1992 | Special Rept:Waste Gas Decay Tank Monitoring Instrumentation Out of Svc for More than 30 Days as Result of Replacement of Pressure Sensors Due to Instrument Drift.Replacement Pumps Received in June 1992.Updated Rept to Be Sent by 920731 | Grab sample |
| ML18153D022 | 3 June 1992 | Special Rept:On 920503,quadrant to Average Power Tilt Exceeded 2% for Greater than 24 H.Caused by Loop Inlet Temp Imbalance.Power Range Nuclear Instruments Recalibr | |
| ML18153C907 | 24 February 1992 | Ro:On 920106,discovered That Portion of Wall Separating Cable Vault & Auxiliary Bldg Was of 4-inch Block Const Instead of Being Designated as Separate Fire Areas.Fire Watches Established Per Station Operating Procedures | Fire Barrier Exemption Request |
| ML18153C737 | 13 September 1991 | Special Rept:On 910815 & 24,quadrant-to-average Power Tilt Exceeded 2% for More than 24 H.Caused by Blown Fuse & Dropped Rod Runback.Cable W/Insulation Damage & Rod Control Cabinet Repaired | Shutdown Margin |
| ML18153C544 | 15 February 1991 | Special Rept:On 901220,spurious Alarms Received Shortly After Placing ATWS Mitigation Sys Actuation Circuitry in Svc.From 901222-28,spurious Trouble Alarms Received.On 901231,improper Voltage Ratings Found on Relay Modules | |
| ML18153C507 | 23 January 1991 | Special Rept:On 901224,quadrant to Average Power Tilt Exceeded 2.0% for Greater than 24 H.Caused by Xenon Transient & Change in Tave Coupled w/pre-existing Core Asymmetry.Isophase Bus Duct Shunts Repaired | |
| ML18152B133 | 5 May 1988 | Ro:Safety Evaluation of Steam Generator Tube Rupture Accident.Continued Operation of Station Based on Continuing Reanalysis of Impact of Steam Generator Tube Uncovery Justified for Listed Reasons | |
| ML18150A163 | 9 June 1987 | Ro:On 870516,automatic Shutdown on Low Reactor Coolant Flow in One Loop Experienced.Caused by Mechanical Failure of Reactor Coolant Loop Stop Valve.Effects of Event from Core DNB Standpoint Evaluated,Per 870527 Telcon W/Nrc | |
| ML18139B988 | 5 August 1982 | Ro:On 820721,rate of Exchange of Condenser Cooling Water Outlet Temp Reached Max of 12 F/Hour Exceeding Max Rate of Change of 3 F/Hour Per Tech Spec 4.14.A.3.Caused by Loss of Electrical Power to Four of Eight Circulating Water Pumps | |
| ML18139B846 | 16 April 1982 | Ro:On 820403,average Rate of Change of Condenser Cooling Water Outlet Temp Exceeded Permitted Rate.Caused by Operator Error.Personnel Reinstructed | |
| ML18139B827 | 26 March 1982 | Ro:On 820212,w/Unit 1 at 100% Power & Unit 2 at Hot Shutdown,Average Rate of Change of Condenser Cooling Water Outlet Temp Exceeded Tech Specs.Caused by Failure of Vacuum Priming Sys at River Intake.Sys Repaired | |
| ML18139B724 | 5 February 1982 | Ro:On 820122,average Rate of Change of Condenser Cooling Water Outlet Temp Exceeded Tech Spec Limit.Caused by Throttling of Water Flow Through Condenser Boxes to Preserve Reduced Canal Water Due to Vacuum Priming Pump Failure | |
| ML18139B499 | 25 August 1981 | Ro:On 810813,condenser Cooling Water Outlet Temp Exceeded Max Rate of Change of 3 F Per Hour Permitted by Tech Spec 4.14.A.3.Caused by Sheared Pin on Condenser Inlet Screen.No Damage to River Environ Found During Search | |
| ML18139B497 | 25 August 1981 | Ro:On 810810,rate of Change of Condenser Cooling Water Outlet Temp Reached Max of 7 F/Hr Exceeding Tech Specs, & Causing Loss of Electrical Svc to 4 of 8 Circulating Water Pumps.Loss of Svc Caused by Ground Fault in Transformer | |
| ML18139B326 | 13 May 1981 | Ro:On 810428,condenser Cooling Water Outlet Temp Exceeded Max Average Rate of Change.Caused by Lack of Svc Water Flow. Event Caused No Detrimental Effect on River Environ | |
| ML18139B287 | 1 May 1981 | Ro:On 810418,condenser Cooling Water Outlet Temp Exceeded Max Average Rate of Change of 3F/hr Per Tech Spec 4.14.A.3. Lack of Svc Water Flow Believed to Be Contributing Factor. Tube Leaks Repaired.River Environ Not Affected | |
| ML18139B250 | 16 April 1981 | Ro:On 810406,condenser Cooling Water Outlet Temp Exceeded Max Average Rate of Change Permitted by Tech Specs.Lack of Svc Water Flow Believed to Be Contributing Factor.Search Conducted to Determine Temp Change Effect on River Environ | |
| ML18139B231 | 1 April 1981 | Ro:On 810322,condenser Cooling Water Outlet Temp Exceeded Tech Spec Limit.Caused by Lack of Svc Water Flow. Investigation Is in Progress | |
| ML18139A964 | 5 January 1981 | Ro:On 801220 at Full Power,Condenser Cooling Water Outlet Temp Exceeded Max Rate of Change Per Tech Specs.Cause Not Stated.Temp Decreased When Waterbox Outlet Valves Throttled Due to Vacuum Priming Problems | |
| ML18139A848 | 19 November 1980 | Ro:On 801102,during Cold Shutdown,Condenser Cooling Water Outlet Temp Exceeded Max Rate of Change of 3 F/Hr.Caused by Lack of Svc Water Flow Through Unit 1.No Detrimental Evidence Found Re River Environ | |
| 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 | |
| ML18139A274 | 23 May 1980 | Ro:On 800512,condenser Cooling Water Outlet Temp Exceeded Temp Change Rate of 3 F/H.During Power Escalation W/Only Three Circulating Water Pumps in Operation,Canal Intake Level Dropped & Groin Temp Reached Change Rate of 5.5 F/H | |
| ML18139A173 | 22 April 1980 | Ro:While Conducting PT 25.12,pump 1-FP-P2 in Fire Protection Sys Failed to Meet Acceptance Criteria of 250 Ft at 2500 Gallons Per Minute.Cause Not Determined.Vendor Will Participate in Insp.Local Fire Depts Will Supply Assistance | |
| ML18136A403 | 18 January 1980 | Ro:On 800108,while Unit 1 Was Operating at 50% Power,Cooling Water Outlet Temp Exceeded 3 F/Hour Change Rate.While Returning Unit 1 to Svc,Discharge Coolant Temp Increased to 7 F/Hour.No Temp Effects on River | |
| ML18136A459 | 16 January 1980 | Ro:On 800116,during Power Operation,Boric Acid Flow in One of Two Required Flow Paths to Core Was Blocked for Approx 3-h.Caused by Inadvertent Closing of Discharge Valve.Valve Immediately Opened & Boric Acid Flow Verified | Boric Acid |
| ML18136A337 | 27 December 1979 | Ro:On 791217,condenser Cooling Water Outlet Temp Exceeded Max Temp Rate Change Permitted by Tech Specs.Caused by Removing Waterbox from Svc Too Rapidly.No Adverse Impact on Environ | |
| ML18136A347 | 10 December 1979 | Ro:On 791207,when Radiation Alarm Setpoint Reached in Discharge Line of Air Ejectors,Trip Valves Diverted Air Into Containment.Caused by Improper Initial Design Concept.Mods to Maintain Valve Closed Initiated | |
| ML18136A231 | 26 November 1979 | Ro:On 791110,condenser Cooling Water Outlet Temp Exceeded Temp Change Rate of 3 F/H While Unit 1 Was at 100% Power & Unit 2 Was in Cold Shutdown.Caused by Valve Misalignment Permitting Sodium Fluid to Enter Sys | |
| ML18136A178 | 9 November 1979 | Ro:On 791026 & 27,condenser Cooling Water Outlet Temp Exceeded Temp Change Rate of 3 F/H.Caused When Waterbox Was Removed from Svc on 791026 & When Returned to Svc on 791027.No Detrimental Effects Found on River Environ | |
| ML18116A174 | 25 June 1979 | RO on 790622:radiography of Facility Steam Generator Feedwater Nozzles & Reducers Revealed Crack Indications at Counterbore Region.Westinghouse & Util to Evaluate Problem | |
| ML18116A175 | 22 June 1979 | RO on 790621:Westinghouse Notified Util of Nonconservatism in Accident Analysis.Increase in Steam Generator Ref Resulted from Rise in Containment Temp Not Properly Accounted For.Corrective Action Being Evaluated | |
| ML18114A698 | 6 June 1979 | RO on 790606:abnormal Degradation of Cable Insulation in Emergency Power Sys Battery Charges.Cause Unknown But Manufacturer Will Be Contacted |