Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20024E7931983-08-19019 August 1983 LER 83-029/03L-0:on 830720,analysis of Central Control Room Air Filtration Sys Charcoal Filters Indicated Absorption Efficiencies for methyl-iodine of 92.9% & 95%.Cause of Inefficiencies Unknown.Charcoal replaced.W/830819 Ltr ML19277C5911983-06-26026 June 1983 LER 83-024/03L-0:on 830527,during Normal Operation,Boron Injection Tank Level Channel 944F Became Inoperable.Caused by Erroneous Level Indication Due to Solidification of Boric Acid in Instrument Line.Affected Line cleared.W/830626 Ltr ML20024A4201983-05-22022 May 1983 LER 83-019/03L-0:on 830422,valve 743,nonautomatic Containment Isolation Valves in RHR Pump Miniflow Line Would Not Operate.Cause Not Stated.Reach Rods Disconnected & Valve Stem & Universal Joints Cleaned & lubricated.W/830522 Ltr ML20024A3461983-05-21021 May 1983 LER 83-014/03L-0:on 830421,charging Pump 21 Developed Leak & Declared Inoperable.Caused by Defective Head Gasket on Cylinder Head 4.Gasket Replaced ML20024A4561983-05-20020 May 1983 LER 83-020/03L-0:on 830420,high Steam Flow Bistable FC449A Setpoint Found Higher than Tech Spec Limit.Caused by Defective Internal Dc Power Supply Board.Board Replaced & Bistable Reset ML20024A5351983-05-19019 May 1983 LER 83-012/03L-0:on 830419,reactor Cavity Continuous Sump Level Monitor LI-3302 Indicated Above 20-ft,but Independent Cavity Level Alarm Did Not Annunciate.Reactor Cavity Found Dry.Caused by Instrument drift.W/830519 Ltr ML20050B3431982-03-23023 March 1982 LER 82-013/03L-0:on 820221,during Normal Operational Testing,Number 23 Svc Water Pump Indicated Vibration of 4.6 Mils.Caused by High Vibration in Pump Gland Seal Area. Packing & Latern Ring Removed,Inspected & Pump Repacked ML20050B2991982-03-19019 March 1982 LER 82-009/01T-0:on 820305,during Power Operation,Nitrogen Pressure Reduction Required Corrective Measures to Prevent Operation in Manner Less Conservative than Assumed in Fsar. Caused by Malfunction of Nitrogen Regulator Valves ML20041E3951982-02-24024 February 1982 LER 82-004/03L-0:on 820125,charging Pump 22 Declared Inoperable Due to Excessive Plunger Seal Leakage.Caused by Normal Wear.Seal Packing Replaced ML20041D6141982-02-18018 February 1982 LER 82-003/03L-0:on 820119,containment Fan Cooler Condensate Flow Monitoring Sys Failed to Operate.Caused by Dry Air Pump,Model 6 Sfcw for Process Radiation Monitors R-11 & 12. Pump Replaced & Returned to Svc ML20041A6051982-02-0505 February 1982 LER 82-001/03L-0:on 820106,steam Generator 23 Level Channel 437B Was Found Drifting in High Level Direction.Caused by Blockage in Impulse Lines to Foxboro Level Transmitter 437B. Lines Blown Out ML20040E4201982-01-21021 January 1982 LER 81-032/03L-0:on 811222,during Testing,Containment Isolation Valve 1723 Found Binding in Midstroke Position. Caused by Binding of Mechanical Linkage Between Grinnell Diaphragm Valve.Linkage Lubricated ML20040D6771982-01-18018 January 1982 LER 81-033/03L-0:on 811217,containment Air Lock Type B Test PT-SA 10 Was Performed 7 Days Late.Cause Not Stated. Followup Sys Revised to Preclude Recurrence ML20039D8941981-12-22022 December 1981 LER 81-010/01T-0:on 811208,leak of Approx 1 Pint Per Minute Identified in Fan Cooler Unit 34.Caused by Leak in Tube of Cooling Coils for Motor Cooler.Tube Repaired ML20039D9001981-12-21021 December 1981 LER 81-030/99X-0:on 811111,seal Return Flow from RCP Increased to Greater than 5 Gpm.Caused by anti-rotation Pin Failure or Seal Failure.New Seals & Pin of Modified Design Installed ML20011A6771981-10-16016 October 1981 LER 81-022/03L-0:on 810916,during Normal Operation W/Reactor at 100% Power,Lubricating Oil of Diesel Generator 21 Had Unusual Appearance.Caused by Leaking Water Into Lube Oil. Cooler Tube Bundle Replaced & Generator Returned to Svc ML20049A8071981-09-21021 September 1981 LER 81-020/03L-0:on 810821,during Normal Operation,Control Rod G-3 Dropped Into Core,Initiating Turbine Runback.Caused by Spray from Leaking Plug Needle Valve on Control Rod H-2, Causing Coil Stack Connector to Fault.Connector Repaired ML20004F6341981-06-12012 June 1981 LER 81-015/03L-0:on 810528,during Low Power Operation, Control Room Instrumentation Indicated Control Rod in Inserted Position.Cause Undetermined.Control Rod Returned to Bank Position.Subsequent Tests Satisfactory ML20004E9291981-06-0303 June 1981 LER 81-013/01T-0:on 810520,low Flow from Two Motor Driven Auxiliary Boiler Feed Pumps at Hot Shutdown Discovered During Surveillance Testing.Caused by New Trim in Generator Level Control Valves Restricting Auxiliary Feedwater Flow ML19259D6931979-10-12012 October 1979 LER 79-022/03L-0:on 790913,amount of Water in Condensate Storage Tank Was 60,000 Gallons Below Tech Spec Requirement. Caused by Efforts to Reduce High Sodium Concentration in Hot Well ML19249B4871979-08-30030 August 1979 LER 79-008/03L-0:on 790803,while Operating at 75% Power,Svc Water Pump 36 Was Smoking at Shaft Packing Gland Area.Caused by Wearing of Line Shafts & Bearings Under Normal Loads.Svc Water Pump Was Replaced ML19289F1211979-06-0909 June 1979 LER 78-020/04T-0 on 780428:activity of Water Sample Taken from Camp Field Reservoir on 780327 Exceeded 10 Times Historical Level.Caused by non-representative Sampling Technique & Adverse Meteorological Conditions ML19282B6741979-03-12012 March 1979 LER 79-001/03L-0 on 790211:high Dew Point & Air Leakage on Breaker 2-6 Noted.To Preclude Breaker Damage,Breaker 2-6 Was Opened.Caused by Apparent Gasket Leak in Westinghouse C-A Breaker.Feeder & Breaker Repaired ML19261B8541979-03-0202 March 1979 LER 79-002/03L-0 on 790205:at 100% Power,Increase in Gaseous Activity Was Observed.Caused by Leakage of No 32 Charging Pump Plunger.Plunger & Packing for Union Pump QX-300 Quintuplex Were Replaced & Unit Returned to Svc ML0936206021979-02-16016 February 1979 LER 79-003/03L-0 on 790120:during Normal Operation,Signal from One of Two Low Level Alarm Devices for Refueling Water Tank Became Erratic,Making Alarm Inoperable.Caused by Freezing of Sensing Line for Level Instrument Controller ML19269D1461979-02-16016 February 1979 LER 79-004/03L-0 on 790126:during Normal Operation,Process Radiation Monitors R-11 & R-12 Became Inoperable Due to Seized Sample Pump.Caused by Seizure of Conde Dry Air Pump, Model 6SFCW,for Process Radiation Monitors R-11 & R-12 ML19269D5651978-11-17017 November 1978 LER 78-034/03L-0 on 781027:increase in Plant Vent Radio Gas Monitor Observed.Caused by Leakage of Charging Pump Plunger 31.Plunger & Packaging for Union Pump QX-300 Quintuplex Replaced.Plunger Returned to Operable Status ML19269D5591978-09-26026 September 1978 LER 78-025/03L-0 on 780831:excessive Noise from Svc Water Pump 35 Observed at 90% Power.Main Pump Shaft Broken, Disabling One of Three Header Pumps.Caused by Bearing Failures.Pump Secured & Header Redirected 1983-08-19
[Table view] Category:RO)
MONTHYEARML20024E7931983-08-19019 August 1983 LER 83-029/03L-0:on 830720,analysis of Central Control Room Air Filtration Sys Charcoal Filters Indicated Absorption Efficiencies for methyl-iodine of 92.9% & 95%.Cause of Inefficiencies Unknown.Charcoal replaced.W/830819 Ltr ML19277C5911983-06-26026 June 1983 LER 83-024/03L-0:on 830527,during Normal Operation,Boron Injection Tank Level Channel 944F Became Inoperable.Caused by Erroneous Level Indication Due to Solidification of Boric Acid in Instrument Line.Affected Line cleared.W/830626 Ltr ML20024A4201983-05-22022 May 1983 LER 83-019/03L-0:on 830422,valve 743,nonautomatic Containment Isolation Valves in RHR Pump Miniflow Line Would Not Operate.Cause Not Stated.Reach Rods Disconnected & Valve Stem & Universal Joints Cleaned & lubricated.W/830522 Ltr ML20024A3461983-05-21021 May 1983 LER 83-014/03L-0:on 830421,charging Pump 21 Developed Leak & Declared Inoperable.Caused by Defective Head Gasket on Cylinder Head 4.Gasket Replaced ML20024A4561983-05-20020 May 1983 LER 83-020/03L-0:on 830420,high Steam Flow Bistable FC449A Setpoint Found Higher than Tech Spec Limit.Caused by Defective Internal Dc Power Supply Board.Board Replaced & Bistable Reset ML20024A5351983-05-19019 May 1983 LER 83-012/03L-0:on 830419,reactor Cavity Continuous Sump Level Monitor LI-3302 Indicated Above 20-ft,but Independent Cavity Level Alarm Did Not Annunciate.Reactor Cavity Found Dry.Caused by Instrument drift.W/830519 Ltr ML20050B3431982-03-23023 March 1982 LER 82-013/03L-0:on 820221,during Normal Operational Testing,Number 23 Svc Water Pump Indicated Vibration of 4.6 Mils.Caused by High Vibration in Pump Gland Seal Area. Packing & Latern Ring Removed,Inspected & Pump Repacked ML20050B2991982-03-19019 March 1982 LER 82-009/01T-0:on 820305,during Power Operation,Nitrogen Pressure Reduction Required Corrective Measures to Prevent Operation in Manner Less Conservative than Assumed in Fsar. Caused by Malfunction of Nitrogen Regulator Valves ML20041E3951982-02-24024 February 1982 LER 82-004/03L-0:on 820125,charging Pump 22 Declared Inoperable Due to Excessive Plunger Seal Leakage.Caused by Normal Wear.Seal Packing Replaced ML20041D6141982-02-18018 February 1982 LER 82-003/03L-0:on 820119,containment Fan Cooler Condensate Flow Monitoring Sys Failed to Operate.Caused by Dry Air Pump,Model 6 Sfcw for Process Radiation Monitors R-11 & 12. Pump Replaced & Returned to Svc ML20041A6051982-02-0505 February 1982 LER 82-001/03L-0:on 820106,steam Generator 23 Level Channel 437B Was Found Drifting in High Level Direction.Caused by Blockage in Impulse Lines to Foxboro Level Transmitter 437B. Lines Blown Out ML20040E4201982-01-21021 January 1982 LER 81-032/03L-0:on 811222,during Testing,Containment Isolation Valve 1723 Found Binding in Midstroke Position. Caused by Binding of Mechanical Linkage Between Grinnell Diaphragm Valve.Linkage Lubricated ML20040D6771982-01-18018 January 1982 LER 81-033/03L-0:on 811217,containment Air Lock Type B Test PT-SA 10 Was Performed 7 Days Late.Cause Not Stated. Followup Sys Revised to Preclude Recurrence ML20039D8941981-12-22022 December 1981 LER 81-010/01T-0:on 811208,leak of Approx 1 Pint Per Minute Identified in Fan Cooler Unit 34.Caused by Leak in Tube of Cooling Coils for Motor Cooler.Tube Repaired ML20039D9001981-12-21021 December 1981 LER 81-030/99X-0:on 811111,seal Return Flow from RCP Increased to Greater than 5 Gpm.Caused by anti-rotation Pin Failure or Seal Failure.New Seals & Pin of Modified Design Installed ML20011A6771981-10-16016 October 1981 LER 81-022/03L-0:on 810916,during Normal Operation W/Reactor at 100% Power,Lubricating Oil of Diesel Generator 21 Had Unusual Appearance.Caused by Leaking Water Into Lube Oil. Cooler Tube Bundle Replaced & Generator Returned to Svc ML20049A8071981-09-21021 September 1981 LER 81-020/03L-0:on 810821,during Normal Operation,Control Rod G-3 Dropped Into Core,Initiating Turbine Runback.Caused by Spray from Leaking Plug Needle Valve on Control Rod H-2, Causing Coil Stack Connector to Fault.Connector Repaired ML20004F6341981-06-12012 June 1981 LER 81-015/03L-0:on 810528,during Low Power Operation, Control Room Instrumentation Indicated Control Rod in Inserted Position.Cause Undetermined.Control Rod Returned to Bank Position.Subsequent Tests Satisfactory ML20004E9291981-06-0303 June 1981 LER 81-013/01T-0:on 810520,low Flow from Two Motor Driven Auxiliary Boiler Feed Pumps at Hot Shutdown Discovered During Surveillance Testing.Caused by New Trim in Generator Level Control Valves Restricting Auxiliary Feedwater Flow ML19259D6931979-10-12012 October 1979 LER 79-022/03L-0:on 790913,amount of Water in Condensate Storage Tank Was 60,000 Gallons Below Tech Spec Requirement. Caused by Efforts to Reduce High Sodium Concentration in Hot Well ML19249B4871979-08-30030 August 1979 LER 79-008/03L-0:on 790803,while Operating at 75% Power,Svc Water Pump 36 Was Smoking at Shaft Packing Gland Area.Caused by Wearing of Line Shafts & Bearings Under Normal Loads.Svc Water Pump Was Replaced ML19289F1211979-06-0909 June 1979 LER 78-020/04T-0 on 780428:activity of Water Sample Taken from Camp Field Reservoir on 780327 Exceeded 10 Times Historical Level.Caused by non-representative Sampling Technique & Adverse Meteorological Conditions ML19282B6741979-03-12012 March 1979 LER 79-001/03L-0 on 790211:high Dew Point & Air Leakage on Breaker 2-6 Noted.To Preclude Breaker Damage,Breaker 2-6 Was Opened.Caused by Apparent Gasket Leak in Westinghouse C-A Breaker.Feeder & Breaker Repaired ML19261B8541979-03-0202 March 1979 LER 79-002/03L-0 on 790205:at 100% Power,Increase in Gaseous Activity Was Observed.Caused by Leakage of No 32 Charging Pump Plunger.Plunger & Packing for Union Pump QX-300 Quintuplex Were Replaced & Unit Returned to Svc ML0936206021979-02-16016 February 1979 LER 79-003/03L-0 on 790120:during Normal Operation,Signal from One of Two Low Level Alarm Devices for Refueling Water Tank Became Erratic,Making Alarm Inoperable.Caused by Freezing of Sensing Line for Level Instrument Controller ML19269D1461979-02-16016 February 1979 LER 79-004/03L-0 on 790126:during Normal Operation,Process Radiation Monitors R-11 & R-12 Became Inoperable Due to Seized Sample Pump.Caused by Seizure of Conde Dry Air Pump, Model 6SFCW,for Process Radiation Monitors R-11 & R-12 ML19269D5651978-11-17017 November 1978 LER 78-034/03L-0 on 781027:increase in Plant Vent Radio Gas Monitor Observed.Caused by Leakage of Charging Pump Plunger 31.Plunger & Packaging for Union Pump QX-300 Quintuplex Replaced.Plunger Returned to Operable Status ML19269D5591978-09-26026 September 1978 LER 78-025/03L-0 on 780831:excessive Noise from Svc Water Pump 35 Observed at 90% Power.Main Pump Shaft Broken, Disabling One of Three Header Pumps.Caused by Bearing Failures.Pump Secured & Header Redirected 1983-08-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H8501999-10-14014 October 1999 Safety Evaluation Supporting Amend 197 to License DPR-64 ML20206U2551999-02-0909 February 1999 Safety Evaluation Supporting Amend 187 to License DPR-64 ML20236Y1571998-08-0303 August 1998 Part 21 Rept Re ASTM A351,GR. CF8 Matl at Indian Point Being Out of Specifications in Molybdenum & Chromium.Cause & Corrective Actions Are Not Stated ML20236V4281998-07-13013 July 1998 Safety Evaluation of TRs WCAP-14333P & WCAP-14334NP, PRA of RPS & ESFAS Test Times & Completion Times. Repts Acceptable ML20236T5511998-06-24024 June 1998 Consolidated Edison Co of Ny,Indian Point Unit 2,Drill Scenario Number 1998C ML20248B2371998-03-31031 March 1998 Revised Monthly Operating Rept for March 1998 for Indian Point Station Unit 2 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML1005008001997-02-28028 February 1997 Conditional Extension of Rod Misalignment TS for Indian Point 3. ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20096E5101995-12-31031 December 1995 Resubmitted Rev 13 to QA Program 05000286/LER-1994-010, :on 941007,concluded That at Least Two EDGs Inoperable During June 1992 Surveillance Test of Carbon Dioxide Fire Protection Sys.Caused by Inadequate Procedural Guidance.Surveillance Test Revised1994-11-0707 November 1994
- on 941007,concluded That at Least Two EDGs Inoperable During June 1992 Surveillance Test of Carbon Dioxide Fire Protection Sys.Caused by Inadequate Procedural Guidance.Surveillance Test Revised
ML17059A3611994-07-0606 July 1994 Emergency Action Level Verification & Validation Rept. ML17311A0181994-05-13013 May 1994 New York State EAL Upgrade Project Verification & Validation Rept. ML20029C7801994-03-31031 March 1994 Monthly Operating Rept for Mar 1994 for Indian Point Unit 1. W/940415 Ltr ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20062J2281993-07-23023 July 1993 Consolidated Edison Co of Ny Indian Point Unit 2,Drill Scenario 1993 ML20044B8461993-03-0404 March 1993 Part 21 Rept Re Possible Safety Implications in Motor Operated Valve Evaluation Software Program Re Use of Total Thrust Multiplier.Utils Advised of Problem & Recommended Corrective Action in Encl Customer Bulletin 92-06 ML20118A2681992-12-31031 December 1992 Consolidated Edison Co of Ny Indian Point,Unit 2 Exercise Scenario,1992 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20096H2301992-05-21021 May 1992 Special Rept:On 920504,south Side Lower Electrical Tunnel Detection Sys 8 Taken Out of Svc for Mod to Reposition Detection Sys Run of Conduit.Detection Sys Declared Operable on 920520 After Mod Completed & Sys Retested ML20079F9181991-05-31031 May 1991 Structural Evaluation of Indian Point,Units 2 & 3 Pressurizer Surge Lines,Considering Effects of Thermal Stratification ML20059E9461990-08-31031 August 1990 Nonproprietary Rev 2 to Indian Point 2 Tube Fatigue Reevaluation ML20059G2011990-07-31031 July 1990 Final Rept on Steam Generator Insp, Repair & Restoration Efforts During 1990 Midcycle Insp ML20058K4121990-06-30030 June 1990 Status Rept,Indian Point Unit 2 Mid-Cycle Steam Generator Insp Presentation to Nrc ML20058K4151990-06-30030 June 1990 Steam Generator Insp,Repair & Restoration Program Presentation to Nrc ML20043A4891990-05-30030 May 1990 Nonproprietary Indian Point Unit 2 Steam Generator Insp, Repair & Restoration Program JPN-90-035, New York Power Authority Annual Rept for 19891989-12-31031 December 1989 New York Power Authority Annual Rept for 1989 ML19332B9371989-11-30030 November 1989 Nonproprietary Info Presented to NRC Re Indian Point Unit 2 Steam Generator Secondary Side Loose Objects. ML19332D6661989-10-31031 October 1989 Nonproprietary Rev 2 to Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage. ML20247J8161989-07-31031 July 1989 Safety Evaluation for UHS Temp Increase to 95 F at Indian Point Unit 3 05000286/LER-1989-013-01, :on 890702,contractor Security Guard Was Found Asleep at Duty Post.Caused by Cognitive Personnel Error. Contract Security Officer Involved in Event Was Dismissed. All Security Personnel Reapprised of Responsibilities1989-07-28028 July 1989
- on 890702,contractor Security Guard Was Found Asleep at Duty Post.Caused by Cognitive Personnel Error. Contract Security Officer Involved in Event Was Dismissed. All Security Personnel Reapprised of Responsibilities
ML20248B3171989-06-30030 June 1989 Rev 1 to Nonproprietary WCAP-12294, Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept,Spring 1989 Outage ML20248D3631989-06-30030 June 1989 Rev 1,to Indian Point Unit 3 Reactor Vessel Fluence & Ref Temp PTS Evaluations ML20247J8071989-05-31031 May 1989 Containment Margin Improvement Analysis for Indian Point Unit 3 ML20247N5331989-05-31031 May 1989 Nonproprietary Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage ML20247G5171989-04-30030 April 1989 Monthly Maint Category I Rept Pages from Monthly Operating Rept for Apr 1989 for Indian Point 05000286/LER-1989-007, :on 890321,unauthorized Access Into Protected Area by Former Employee Utilizing Photo Identification Badge of Another Contract Employee Occurred.Caused by Security Guard Error.Security Retrained1989-04-17017 April 1989
- on 890321,unauthorized Access Into Protected Area by Former Employee Utilizing Photo Identification Badge of Another Contract Employee Occurred.Caused by Security Guard Error.Security Retrained
ML20244C3311989-04-10010 April 1989 Safety Evaluation Supporting Amend 137 to License DPR-26 ML20248F4211989-03-31031 March 1989 NSSS Stretch Rating-3,083.4 Mwt Licensing Rept 05000286/LER-1989-001, :on 890204,initiated Safety Injection Via High Steam Flow Safety Injection Logic.Caused by Uneven Refilling of Steam Flow Instrumentation Lines.Safety Injecton Terminated & Plant Cooldown Proceeded1989-03-0303 March 1989
- on 890204,initiated Safety Injection Via High Steam Flow Safety Injection Logic.Caused by Uneven Refilling of Steam Flow Instrumentation Lines.Safety Injecton Terminated & Plant Cooldown Proceeded
ML20235V5931989-03-0202 March 1989 Special Rept:During Cycle 6/7 Refueling Outage Scheduled from Feb-May 1989,openings Will Be Made in Plant Penetration Fire Barriers in Order to Install Various Mods. Fire Watches Posted & Fire Detection Tests Completed 05000286/LER-1989-003-01, :on 890205,security Gate Found Unlocked.Caused by Cognitive Personnel Error.Upgrade of Security Procedure 4, Compensatory Measures to Clearly Define Methods of Establishing,Maintaining & Closing Posts Performed1989-02-23023 February 1989
- on 890205,security Gate Found Unlocked.Caused by Cognitive Personnel Error.Upgrade of Security Procedure 4, Compensatory Measures to Clearly Define Methods of Establishing,Maintaining & Closing Posts Performed
ML20246E2711988-12-31031 December 1988 Con Edison 1988 Annual Rept ML20248F3001988-12-31031 December 1988 10CFR50.59(b) Rept of Changes,Tests & Experiments Completed in 1988 ML20196D3011988-10-31031 October 1988 Reactor Vessel Matl Surveillance Program for Indian Point Unit 2 Analysis of Capsule V ML20155H2541988-09-30030 September 1988 Rev 2 to Indian Point Unit 2 (NRC Bulletin 88-008 Thermal Stresses in Piping Connected to RCS) Indentification of Unisolable Piping & Determination of Insp Locations ML20154M5661988-08-31031 August 1988 Monthly Operating Rept for Aug 1988 for Indian Point Station Unit 2 1999-02-09
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