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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20077B473 | 10 May 1991 | Ro:On 910507,operator Failed to Perform Surveillances & Channel Tests for All 6 Scram Channels & 2 Interlocks Prior to Reactor Operation.Caused by Personnel Error. Tailgate Meeting Held & Mods to Hardware Initiated | |
| BECO-86-173, Partially Withheld Security Event Rept:On 861107,HVAC Duct, Penetrating Vital Area,Removed by Contracted Craft Workers Before Notifying Security.Cause Not Stated.Security Oversight of Subj Contract Work Intensified | 12 November 1986 | Partially Withheld Security Event Rept:On 861107,HVAC Duct, Penetrating Vital Area,Removed by Contracted Craft Workers Before Notifying Security.Cause Not Stated.Security Oversight of Subj Contract Work Intensified | |
| BECO-86-171, Partially Withheld Security Event Rept:On 861106,temporary Vital Area Barrier Insp Found Barrier Could Be Breached. Barrier Modified & Compensatory Security Measures Released | 10 November 1986 | Partially Withheld Security Event Rept:On 861106,temporary Vital Area Barrier Insp Found Barrier Could Be Breached. Barrier Modified & Compensatory Security Measures Released | |
| ML20211E073 | 26 September 1986 | Unplanned Operating Event Rept 85-6, Manual Reactor Trip Following MSIV Closure Due to Inadvertent Emergency Feedwater Actuation,851009 | |
| BECO-86-125, Partially Withheld Security Event Rept:On 860826,bomb Threat Received.Search Initiated.No Suspicious Objects Found | 29 August 1986 | Partially Withheld Security Event Rept:On 860826,bomb Threat Received.Search Initiated.No Suspicious Objects Found | |
| ML20238E460 | 28 August 1986 | Partially Withheld Secrity Event Rept:On 860824,bomb Threat Received for Plants.Bomb Search Initiated.No Suspicious Objects Found | |
| ML20212Q697 | 26 August 1986 | Ro:On 860821,during Prestartup,Source Interlock Operated But Failed to Prevent Movement of Control Rods.Caused by Temporary Loss of Electrical Contact in Logic Circuits. Movement Restored Proper Electrical Contact | |
| ML20211K821 | 18 June 1986 | Special Rept:On 860521,valid Failure Occurred on Div 2 Diesel Generator During Performance of Tech Spec Surveillance 4.8.1.1.2.Caused by Failure of Jacket Water Thermostatic Control Valve to Open | |
| ML20238E459 | 17 June 1986 | Partially Withheld Security Event Rept:On 860612,withheld Discovery Made Re 860604 Moderate Loss of Security Effectiveness.Caused by Inadequate Post Orders & Training for Assignment.Assignments Will Be Specifically Addressed | |
| 05000000/LER-1986-009, Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised | 14 April 1986 | Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised | |
| BECO-86-016, Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended | 20 February 1986 | Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended | |
| BECO-85-220, Partially Withheld Security Event Rept:On 851204 Vertical Pipe Chase Not Locked.Lock Removed When Surveys Indicated Radiation Level Below Requirement for Locked High Radiation Level.Pipe Chase Will Be Secured | 9 December 1985 | Partially Withheld Security Event Rept:On 851204 Vertical Pipe Chase Not Locked.Lock Removed When Surveys Indicated Radiation Level Below Requirement for Locked High Radiation Level.Pipe Chase Will Be Secured | |
| ML20136H329 | 13 November 1985 | Ro:On 851112,wide-range Log Channel Malfunctioned During Operation of Reactor.Caused by Faulty Calibr Switch in Log Channel.Switch Adjusted & Reactor Operated at Several Power Levels Up to 95 Kw | |
| ML20114B322 | 14 January 1985 | Ro:On 850107,while Taking Unit to 95 Kw Power,Period Meter Indicated Period Decreasing W/Log Power Trace Levelling & Linear Power Trace Rising.Caused by wide-range Log Channel Malfunction.Manual Scram Initiated & Reactor Secured | |
| ML20101M849 | 10 December 1984 | Ro:On 841203,wide-range Log Channel Malfunctioned,Resulting in Manual Scram.Cause Traced to Resistor in Filter on Detector High Voltage Supply.Repairs & Testing in Progress | |
| AECM-84-0204, Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored | 6 April 1984 | Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored | |
| ML20198H369 | 14 November 1983 | Ro:On 831003,results of as-found Tests Indicated Crosby Main Steam Relief Valves Had Lift Points Exceeding Tech Spec Limits.Valves Disassembled & Rebuilt by Mfg | |
| 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 |
| ML20065R400 | 20 October 1982 | Ro:On 821006,malfunction of Eberline AMS-3 Continuous Air Monitor Pump Caused Pump to Be Inoperable for Approx 1-h.No Loss of Significant Signals Indicated.Pump Repaired.Changes to Procedures or Equipment Under Review | |
| ML20137G450 | 24 March 1981 | Ro:During walk-through of Operator Training Program, O-ring Seal of Filter Holder Found Not Seated Properly Causing Partial Bypass of Filter for Air Sucked Into instrument.Filter-in Lock Adjusted | |
| ML20071F086 | 25 September 1980 | Ro:On 800912,sample Analysis Taken from Hydrazine Addition Tank Indicated Sodium Chloride in Tank.Anonymous Telcon Indicated Salt May Have Been Added Prior to Labor Strike by Unknown Persons | |
| ML20086D514 | 6 January 1978 | Telecopy Ro:On 780105,discovered That One of Two Nuclear Engineering Co Model B3-1 Shipping Casks Provided w/1-inch Diameter Lid Bolts Rather than 1-1/4 Inch Size Specified in Certificate of Compliance 6058 | |
| ML20086D520 | 14 December 1977 | Telecopy Ro:Heating Steam Coil Leak in Reactor Bldg Ventilation Supply Unit V-AH-4A Resulted in Freezing of Condensate at Inlet to Unit & Subsequent Inoperability of Associated Secondary Containment Isolation Dampers | |
| ML20086D537 | 14 October 1977 | Telecopy Ro:Insp of Internal Torus Catwalk Support Structure Revealed That Catwalk Mitered Sections Not All Attached to Horizontal Catwalk Support Plates in Some Manner.Attachment Locations Will Be Upgraded | |
| ML20086D550 | 13 October 1977 | Telecopy Ro:On 771012,local Leak Rate Testing of MSIV AO-2-80A & Nitrogen Instrument Air Sys Isolation Valve CV-7436 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation | |
| ML20086D554 | 5 October 1977 | Telecopy Ro:On 771004,local Leak Rate Testing of HPCI Sys Discharge Isolation Check Valve HPCI-9 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation | |
| ML20086D557 | 29 September 1977 | Telecopy Ro:On 770929,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO-14-13A Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation | |
| ML20086D561 | 14 September 1977 | Telecopy Ro:On 770913,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO 14-13B Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Related Event on 770914 | |
| ML20086D567 | 12 September 1977 | Telecopy Ro:Main Steam Drain Isolation Valve MD 2373 & Main Steam Outboard Isolation Valve AO 2-86A Exceeded Tech Spec Acceptance Criteria for Local Leak Rate Tests | |
| ML20086D642 | 11 July 1977 | Telecopy Ro:On 770709,determined That Recombiner Sys a Offgas Flow Control Valve PCV 7489A Could Be Opened W/ Controlling Solenoid Valve Deenergized.Valve Held from Svc Pending Investigation | |
| ML20137G446 | 23 June 1977 | Ro:On 770621,radioactive Source Containing 200 Mci Cs-137 Recovered from Brine Well 33.Incident Described in | |
| ML20086F080 | 6 June 1977 | Ro:On 770506,plant Iodine & Particulate Release Rate Exceeded 4% of Facility Tech Spec Averaged Over Second Calendar Quarter of 1977.Caused by Fuel Perforations Coupled W/End of Cycle Testing & Reactor Coolant & Steam Leaks | Fuel cladding |
| ML20086D691 | 2 March 1977 | Telecopy Ro:On 770301,torus Water Vol Found to Be Slightly Below Min Vol Established by Tech Specs.Water Vol Restored to Normal Operating Level | |
| ML20086D703 | 24 February 1977 | Telecopy Ro:On 770223,while Withdrawing in-sequence Control Rod to Bring Reactor Critical,Reactor Period of Less than 5 Obtained | |
| ML20086F418 | 9 December 1976 | RO Re Plant Iodine & Particulate Release Rate Exceeding 4% of Tech Spec 3.8.C.2 Averaged Over Fourth Calendar Quarter 1976.Caused by Leaks in Reactor Water Cleanup Sys.Leaks Repaired & Equipment Modified to Reduce Leakage | |
| 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 | |
| ML20086D788 | 10 September 1976 | Telecopy Ro:On 760909,discovered That Torus Water Vol Several Hundred Cubic Ft Below 68,000 Cubic Ft Min Required by Tech Specs.Caused by Failure to Correct for Vol Vs Level Correlation | |
| ML20086D823 | 5 May 1976 | Telecopy Ro:On 760504,during Routine Surveillance Test, Primary Containment Oxygen Concentration Found to Be in Excess of Tech Spec Limit.Caused by Leakage from Drywell Instrument Air Sys Into Containment Nitrogen Supply Line | |
| ML20086F470 | 27 January 1976 | Ro:On 760117,gaseous Activity Release Rate Exceeded 4% of Tech Spec 3.8.C.1 for More than 48 H.Caused by Increase in Offgas Activity Due to Fuel Cladding Perforations | Fuel cladding Power change |
| ML20137H384 | 12 January 1976 | Ro:On 760106,operator Left Console Key in Switch So That Reactor Not Secured Per Tech Specs.Key Withdrawn from Console.Incident Discussed W/Operators & Large Red Plastic Tag Attached to Key to Make It More Visible | |
| ML20086F473 | 23 December 1975 | Ro:On 751123,during Insp of Upper Portions of Drywell,Two of Eight Reactor Vessel Stabilizers Appeared to Have Been Slightly Deformed.Caused by Stabilizer Bindup & Cyclic Loading During Vessel Heatup or Cooldown | |
| ML20085E953 | 4 July 1975 | Telecopy Message of Ro:On 750703,facility Became Inoperable Due to Governor Problems.Manual Operation Possible.Lee Gas Turbine Could Not Be Tied in Through Isolated Line to Supply & Buy Power.Investigation Continuing | |
| ML20084K741 | 19 September 1974 | Telecopy Ro:On 740913,plant Shut Down to Investigate Source of Unidentified Leak in Drywell.Caused by Small Crack Through Pipe Wall in 4-inch Bypass Line on B-recirculation Loop.Ge Investigation Initiated | Safe Shutdown |
| ML20084K773 | 13 September 1974 | Telecopy Ro:On 740913,unit Shut Down Upon Discovery of Leak on 2B Recirculation Pump Loop at Junction of Discharge Line & Recirculation Loop Between Pump & Discharge Valve. Investigation Continuing | Time of Discovery |
| ML20084D018 | 11 June 1974 | Telecopy Message of Ro:On 740611,8 of 31 Bergen-Paterson Hydraulic Piping Restraints within Drywell Found Defective. Caused by Loss of Hydraulic Fluid & Vibration of Cleanup Sys Header within Drywell.Repairs Initiated | |
| ML20084D010 | 11 June 1974 | Telecopy Message of Ro:On 740611,8 of 31 Bergen-Paterson Hydraulic Piping Restraints within Drywell Found Defective. Caused by Loss of Hydraulic Fluid & Vibration of Cleanup Sys Header within Drywell.Repairs Initiated | |
| ML20084D040 | 13 February 1974 | Telecopy Message of Ro:On 740211,12 of 31 Bergen-Paterson Hydraulic Piping Restraints within Drywell Found Defective Caused by Loss of Hydraulic Fluid.Restraints to Be Overhauled |