Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
ML20132B3296 December 1996Special Rept:On 961113,operator Discovered Control Switch for Diesel Output Breaker in pull-to-lock Position. Investigation Was Performed to Determine How Long Aac DG Was Inoperable
ML20112F68411 December 1984Special Rept SR-84-4:on 841015,process Vent High Range RM-GW-130-2 & Ventilation Vent High Range RM-VG-131-2 Effluent Monitors Inoperable.Cause Under Investigation. Alternate Methods of Monitoring Gaseous Effluents Confirmed
ML20081B61724 February 1984RO SPR-84-003:on 840206,following Trip from 100% Power, Specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Limit of Less than or Equal to 1.0 Uci.Caused by Fuel Element Defects in Reactor Core
ML20087B61817 February 1984RO SPR-84-2:on 840118,specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level of 1.89 Uci,Exceeding Tech Spec Limit.Caused by Fuel Element Defects in Reactor Core.Dose Level Monitored
ML20080N33913 February 1984RO SPR-84-1:on 840106,specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level Exceeded Tech Spec Limits.Caused by Known Fuel Element Defects in Core.Tech Spec Requirements Implemented
ML20105D24324 June 1983Special Rept:Five Individuals Found to Have Received Radiation in Excess of 10CFR20.101 Limits W/O Required Documentation.Caused by computer-based Sys Feature Allowing Use of Outdated Info & Personnel Error.Procedures RevisedHigh Radiation Area
Locked High Radiation Area
05000280/LER-1977-012, RO S1-77-01 Re Failures of Hydraulic Shock Supports (Snubbers).Extent of Failures Reported in LER 77-12.All Snubbers Operable on 771207 Startup5 January 1978RO S1-77-01 Re Failures of Hydraulic Shock Supports (Snubbers).Extent of Failures Reported in LER 77-12.All Snubbers Operable on 771207 Startup
ML20086S09430 September 1977RO S2-77-01, Missing Steam Generator Tube Plug-Hot Leg,Generator B,Row 1,Column 42Hydrostatic
ML20070J86820 October 1976RO 76-13:on 760916,normal Boric Acid Makeup to Vol Control Tank Could Not Be Accomplished Due to Plugging of Chemical & Vol Control Sys Line 1-inch-CH-56-152.Cause Unknown.Line Will Be Inspected for Indications of SolidificationBoric Acid
ML20070J8581 October 1976RO 76-12:on 760909,low Pressure Alarm Occurred on Safety Injection Accumulator C,Resulting in Pressure Reduction. Caused by Partially Open HCV 1936 & Body to Bonnet Leaks on HCV 1898 & 1549.Valves Repaired & Accumulator Repressurized
ML20070J89629 September 1976RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated
ML20070J88024 September 1976RO 76-07:on 760913,monthly Average of Gaseous & Airborne Particulate Wastes for Previous 12 Months Found Greater than Tech Spec Limit.Caused by Interpretational Changes in Tech Spec Section 3.11.B.New Limit Approved
ML20086S55117 August 1976SR-S2-76-01 Re Summary of Analysis & Interpretation of Type A,B & C Containment Leak Rate Test Results Obtained During Refueling Outage.No Evidence of Structural Deterioration Found
ML20086Q2551 July 1976Supplemental Rept to SR-S1-75-08 on Containment Leak Rate Testing Including Errors Inherent in Correlating Type a Leakage Test W/Type B & C Tests & Instrument Error Analysis
ML20086S7017 May 1976Suppl 1 to USRE-S1-76-01:751204,no Air Flow Indicated from Local Flow Indicator on Containment Gaseous & Particulate Monitor Cabinet.Caused by Failed Bearing on Vacuum Pump. Bearing Replaced & Pump Tested Satisfactorily
ML20086S5911 April 1976Ro:On 760322 & 23,temp Difference Across Station Exceeded 15 F.Caused by Rapid Drop in River Water Ambient Temp Making Prediction When Action Necessary to Avoid Temp Increase Difficult
ML20086S6984 February 1976Telecopy Ro:On 760204,main Steam Trip Valve TV-MS-201A Failed to Close When Operated from Control Room.Cause Under Investigation
ML20086S7093 February 1976USRE-S1-76-01:on 751204,no Air Flow Indication Found from Local Flow Indicator on Containment Gaseous & Particulate Monitor Cabinet.Caused by Failed Bearing on Vacuum Pump. Bearing Replaced & Pump Tested SatisfactorilyBoric Acid
ML20087B79228 November 1975SR-S1-75-07:on 751025,during Movement of Manipulator Crane, Manipulator Outer Cast Inadvertently Driven Into Upper Internals Package & Damaged Drive Shaft at Core Location P-8.Drive Line Tested & Acceptable for Reuse
ML20087B78726 November 1975SR-S1-75-06:on 751021,discovered Tube R19C74 Severely Distorted & Stretched During Removal of Tube Sample on Steam Generator A.Caused by Malfunction of Internal Tube Cutter. Tube Plugged as Precautionary Measure
ML20087B68615 September 1975SR-S1-75-04:on 750730 & 0804,I-131 Activity Revealed to Be 8.04% of Tech Spec Limit.Caused by Containment Purging Operation & Fitting Leak on Overhead Gas Compressor. Containment Purge Terminated & Compressor Isolated
ML20087C13915 September 1975Ro:On 750802 & 03,condenser Cooling Water Discharge Temp Exceeded 98 F for More than 3 H.Caused by Rising River Water Temp.Util Requested & Was Granted Emergency Relaxation of Tech Spec 4.14.A.1 Effective Until 750806
ML20087C17825 July 1975SR-S1-75-03:on 750709,I-131 Activity Found to Be 4.6% of Tech Spec Limit.Caused by Containment Purging Operations & Containment Maint Activities.Containment Purge Exhaust Diverted Through Charcoal Filter Sys
ML20087C21530 June 1975SR-S1-75-02:on 750502,rate of Liquid Waste Release Increased to 10% of Tech Spec Limit to Reduce Quantity of Stored Liquid Waste.On 750514,I-131 Activity Found at 6.5% of Tech Spec Limit
ML20086Q4722 June 1975SR-S2-75-02:during Refueling,Fuel Assembly N-20 Incurred Damage to Two of Four Holddown Springs on Top Nozzle Assembly.Fuel Assembly Acceptable for Power Operation in Cycle 2
ML20086Q4152 June 1975SR-S2-75-01:during Refueling Operation,Cladding Perforation Detected on Fuel Assembly N-10.Fuel Assembly Can Be Safely Operated to end-of-Cycle 2 Design Burnup
ML20086R19810 April 1975USRE-S2-74-01:on 740214,alarm Received Indicating Low Discharge Flow in Containment Vacuum Sys.Caused by Containment Vacuum Pumps Discharging Air.Pumps Removed & Spare Pump InstalledLoop seal
ML20086Q7148 April 1975URSE-S2-74-01:on 740214,alarm Received Indicating Low Discharge Flow in Containment Vacuum Sys.Cause Not Determined.Pumps Disassembled,Inspected,Cleaned & Reassembled
ML20086Q8374 March 1975SR-S1-75-05:on 750929,routine Sampling of Ventilation Vent Gaseous Activity Revealed I-131 Activity in Excess of 4% of Tech Spec Limit.Caused by Containment Purging Operations, Filter Problems & Leakage & Treatment of Radioactive Water
ML20086Q99724 February 1975SR-S1-75-01:on 741120,45 Concrete Blocks Fell Into Reactor Cavity.Reactor Vessel or Associated Sys Not Damaged & All Debris Removed
ML20086R1263 February 1975Ro:On 750128,newly Installed Fish Screens at Intakes Allowed Average of 89% of Fish Impinged During Period to Return to River Alive.Incident Not Considered to Have Caused Significant Mortality.Fish Mortality Data Encl
ML20086S38224 January 1975SR-S1-74-06:damage Discovered on Pipe Restraint Anchors on Safety Injection Accumulator Discharge Lines.Caused by Flashing & Water Hammer Shock Experiences During Early Operation
ML20086S41210 January 1975SR-S1-74-04:on 740904,sampling of Ventilation Vent Activity Revealed I-131 Activity of 5.8% of Tech Spec Limit.Caused by High Activity of Steam Generator a Blowdown Vent.Primary to Secondary Tube Leak Repaired
ML20086S30313 December 1974USRE-S1-74-03:on 741107,small Amount of Low Level Radioactivity Released to James River Via Component Cooling Svc Water.Caused by Inoperability of Pump 1-SW-P-6 Due to Lack of Water Lubrication
ML20086S28029 November 1974SR-S1-74-05:deterioration of Steam Generator Tubes Noted. Caused Not Determined.Sludge Deposits & Deleterious Effect of Sodium Phosphate Chemistry Control Contributed to Magnitude & Rate of Deterioration
ML20086S37829 November 1974SR-S2-74-01:pipe Restraints on Three Safety Injection Accumulator Discharge Lines Experienced Some Degree of Shock & Vibration.Caused by Flashing & Water Hammer Shock Experienced During Early OperationLiquid penetrant
ML20086S57419 September 1974USRE-S1-74-01:discovered Two Singular Pipe Runs Passing Through Respective Containment Boundary W/Check Valves on Either Side of Containment.Caused by Oversight in Design. Four Check Valves Will Be Installed
ML20086S47326 August 1974Ro:On 740725 & 26,liquid Release Occurred Which Exceeded 4% of Tech Spec Limit.Steam Generator Leakage Being Continuously Monitored & Will Be Repaired During 741015 Refueling Shutdown
ML20086S97215 July 1974SR-S1-74-01:on 740526,reactor Vessel Leakoff High Temp Alarm Received.Caused by Inadequacy of Packing Mfg by J Crane Co. Packing Will Be Replaced W/Grafoil Packing
ML20215H50916 August 1972Ro:On 720727,during Shutdown,Two Employees Injured When Steam Vent Sys Malfunctioned.Caused by Decay Heat Release Piping Disengaging from Piping Support Sys.Workers Treated for Burns.Design Change Investigated.News Release Encl
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BCategory:REPORTABLE-20OCCURRENCE-20REPORT-20(SEE-20ALSO-20AO-20LER)-5D-5D-20-5B-5BSite::Surry-5D-5D/-3FIssue-20date/-3FTitle/-3FTopic/mainlabel%3D/order%3D-20descending/sort%3D-20Issue-20date/offset%3D0/format%3Dtable/searchlabel%3D-5BTable-20view-5D"