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Issue date | Title | Topic | |
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ML20132B329 | 6 December 1996 | Special 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 | |
ML20112F684 | 11 December 1984 | Special 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 | |
ML20081B617 | 24 February 1984 | RO 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 | |
ML20087B618 | 17 February 1984 | RO 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 | |
ML20080N339 | 13 February 1984 | RO 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 | |
ML20105D243 | 24 June 1983 | Special 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in Excess of 10CFR20.101 Limits W/O Required Documentation.Caused by computer-based Sys Feature Allowing Use of Outdated Info & Personnel Error.Procedures Revised | High Radiation Area Locked High Radiation Area |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 Startup | 5 January 1978 | RO S1-77-01 Re Failures of Hydraulic Shock Supports (Snubbers).Extent of Failures Reported in LER 77-12.All Snubbers Operable on 771207 Startup | |
ML20086S094 | 30 September 1977 | RO S2-77-01, Missing Steam Generator Tube Plug-Hot Leg,Generator B,Row 1,Column 42 | Hydrostatic |
ML20070J868 | 20 October 1976 | RO 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 Solidification | Boric Acid |
ML20070J858 | 1 October 1976 | RO 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 | |
ML20070J896 | 29 September 1976 | RO 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 | |
ML20070J880 | 24 September 1976 | RO 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 | |
ML20086S551 | 17 August 1976 | SR-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 | |
ML20086Q255 | 1 July 1976 | Supplemental 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 | |
ML20086S701 | 7 May 1976 | Suppl 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 | |
ML20086S591 | 1 April 1976 | Ro: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 | |
ML20086S698 | 4 February 1976 | Telecopy Ro:On 760204,main Steam Trip Valve TV-MS-201A Failed to Close When Operated from Control Room.Cause Under Investigation | |
ML20086S709 | 3 February 1976 | USRE-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 Satisfactorily | Boric Acid |
ML20087B792 | 28 November 1975 | SR-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 | |
ML20087B787 | 26 November 1975 | SR-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 | |
ML20087B686 | 15 September 1975 | SR-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 | |
ML20087C139 | 15 September 1975 | Ro: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 | |
ML20087C178 | 25 July 1975 | SR-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 | |
ML20087C215 | 30 June 1975 | SR-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 | |
ML20086Q472 | 2 June 1975 | SR-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 | |
ML20086Q415 | 2 June 1975 | SR-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 | |
ML20086R198 | 10 April 1975 | USRE-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 Installed | Loop seal |
ML20086Q714 | 8 April 1975 | URSE-S2-74-01:on 740214,alarm Received Indicating Low Discharge Flow in Containment Vacuum Sys.Cause Not Determined.Pumps Disassembled,Inspected,Cleaned & Reassembled | |
ML20086Q837 | 4 March 1975 | SR-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 | |
ML20086Q997 | 24 February 1975 | SR-S1-75-01:on 741120,45 Concrete Blocks Fell Into Reactor Cavity.Reactor Vessel or Associated Sys Not Damaged & All Debris Removed | |
ML20086R126 | 3 February 1975 | Ro: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 | |
ML20086S382 | 24 January 1975 | SR-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 | |
ML20086S412 | 10 January 1975 | SR-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 | |
ML20086S303 | 13 December 1974 | USRE-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 | |
ML20086S280 | 29 November 1974 | SR-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 | |
ML20086S378 | 29 November 1974 | SR-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 Operation | Liquid penetrant |
ML20086S574 | 19 September 1974 | USRE-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 | |
ML20086S473 | 26 August 1974 | Ro: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 | |
ML20086S972 | 15 July 1974 | SR-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 | |
ML20215H509 | 16 August 1972 | Ro: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 |