ML20041E206
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| ML20041E206 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 02/24/1982 |
| From: | Matthew Smith CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20041E194 | List: |
| References | |
| LER-81-004-03L, LER-81-4-3L, NUDOCS 8203100245 | |
| Download: ML20041E206 (1) | |
Similar Documents at Indian Point | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20024E7931983-08-19019 August 1983
[Table view]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 ML20024A3841983-05-27027 May 1983 LER 83-015/03L-0:on 830427,shutdown Initiated When Containment Spray Pump 21 Did Not Meet Operability Criteria. Repairs Not Completed within Allowable Time Period.Caused by High Vibrations.Pump replaced.W/830527 Ltr ML20024A3791983-05-22022 May 1983 LER 83-017/03L-0:on 830422,leak Observed in Isolation Valve Seal Water Sys.Caused by Damage to 3/8-inch Stainless Steel Weld Connection FW10016.Weld repaired.W/830522 Ltr ML20024A3831983-05-22022 May 1983 LER 83-021/03L-0:on 830422,analysis Revealed Adsorption Efficiency for Methyl Iodine of 82.2%.Cause Under Investigation.Charcoal Filters replaced.W/830522 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 ML20024A5171983-05-22022 May 1983 LER 83-016/03L-0:on 830422,boron Injection Tank Level Channel 944F Became Inoperable.Caused by Erroneous Level Indication Due to Boric Acid Solidification in Instrument Impulse Line.Affected Impulse Line cleaned.W/830522 Ltr ML20024A5291983-05-22022 May 1983 LER 83-018/03L-0:on 830422,plant Shutdown Commenced When Binding of Valve 1870 Could Not Be Corrected within Tech Spec Time Period.Cause Not Stated.Binding Alleviated by Lubricating Valve Stem & Universal joints.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 ML20024A5241983-05-20020 May 1983 LER 83-013/03L-0:on 830420,during Surveillance Testing of Containment Isolation Valves,Valve 1702 Did Not Fully Close. Cause Not Stated.Shaft & Inside of Actuator Cleaned.Air Motor Diaphragm Replaced as Preventive measure.W/830520 Ltr 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 ML20027B9071982-09-16016 September 1982 LER 82-037/99X-0:on 820902,svc Water Leak Identified on Reactor Containment Fan Cooler Unit 22.Cause Under Investigation.Leakage Will Be Closely Monitored & Failed Tubes Examined During Upcoming Refueling Outage ML20052B8631982-04-19019 April 1982 LER 82-014/03L-0:on 820320,valve 267A Found Leaking.Two Boric Acid Transfer Pumps & Boric Acid Storage Sys Isolated in Order to Isolate Valve for Repairs.Caused by Diaphragm Failure.Valve Repaired ML20050D5251982-03-26026 March 1982 LER 82-008/03L-0:on 820224,during Routine Insp,Three Lines in Rack 15 of Weld Channel & Containment Penetration Sys Were Isolated.Cause Not Stated.Affected Lines Promptly Returned to Svc & Sys Checked to Assure Proper line-ups ML20050C0821982-03-24024 March 1982 LER 82-010/01T-0:on 820310,determined That Existing Operating Procedures Required Necessary Safeguards Equipment to Be Operable Prior to Bringing Reactor Critical But Did Not Establish Specific Requirements in Hot Shutdown 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 ML20050B3141982-03-19019 March 1982 LER 82-007/03L-0:on 820217,during Visual Insp of Number 21 Battery Cell,Number 31 Cell Found Leaking & Exhibiting Low Electrolyte Level.Caused by Cell Casing Crack Due to Expansion of Positive Plates.Cell Replaced 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 ML20042A6831982-03-0909 March 1982 LER 82-006/03L-0:on 820207,power Range Nuclear Instrumentation Channel N 43 Indicated High & Then Became Erratic.Cause Not Given.Channel Returned to Normal During Operation.Instrumentation to Be Closely Monitored ML20042A2461982-03-0808 March 1982 LER 82-005/03L-0:on 820206,main Steam Isolation Valve Dwg 20728-B for Loop 23 Failed to Close During Isolation of Secondary Plant for Maint.Caused by Insufficient Packing Lubrication.Packing Lubricated & Valve Stroked ML20041E2021982-02-24024 February 1982 Updated LER 81-003/03L-1:on 810119,during Surveillance Test PT-R35 Shutoff Valve 822B in Component Cooling Water Return Line 21 for RHR Heat Exchange Would Not Open.Caused by Loose Torque Switch.Switch Tightened 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 ML20041E2061982-02-24024 February 1982 Updated LER 81-004/03L-1:on 810119,during Surveillance Test PT-R35 Opening Time for One of Two Power Operated Relief Valves (PCV-456) Was 2.5-s Longer than Permitted.Caused by Nitrogen Supply Valve Inadvertently Closed.Valve Reopened 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 ML20041B2321982-02-0909 February 1982 LER 82-002/03L-0:on 820110,during Full Power Operation,Weld Channel & Penetration Pressurization Sys Air Consumption Exceeded Tech Spec Limits.Caused by Excessive Seat Leakage in Fischer Valve 1192.Valve Removed & Seat Replaced 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 ML20040E4311982-01-21021 January 1982 LER 81-031/03L-0:on 811223,during Surveillance Test PT-MI/PC-MI at 100% Power,Value for Q (Upper) on Channel N44 Was Found Incorrect.Caused by Transcription Error.Channel Recalibr & Retested Satisfactorily 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 ML20039D9121981-12-21021 December 1981 LER 81-029/03L-0:on 811119,during Test Run of Safety Injection Pump,Motor Emitted Smoke & Did Not Turn.Caused by Frozen Shaft Bushings on Pump Rotating Elements.Pump Replaced ML20039D9081981-12-21021 December 1981 LER 81-028/03L-0:on 811120,pressurizer Safety Valve PCV-464 Found to Actuate Approx 4% Below Tech Spec Min.Cause Unknown.Valve Readjusted & Retested 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 ML20039B5971981-12-10010 December 1981 LER 81-027/03L-0:on 811110,primary Heat Trace Circuit for Balance Leakoff Line of Safety Injection Pump 23 Failed. Caused by Burned & Broken Connection at Chromalox Strip Heater Element for Thrust Balance Line ML20039B1581981-12-10010 December 1981 LER 81-009/03L-0:on 811110,battery Charger 31 Tripped.Cause Not specified.Delta-P Air Flow Sensing Switch Replaced ML20038B8141981-11-24024 November 1981 LER 81-026/03L-0:on 811029,reduction Observed in Delta & Average Temp on Loop 23.Caused by Defect in Hot Leg Model 176JA Resistance Temp Detector Circuit.Resistance Temp Element Replaced 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 ML20010H7531981-09-14014 September 1981 LER 81-021/99X-0:on 810829,pinhole Leak Discovered in Elbow on 2-inch Svc Water Outlet Line.Caused by Erosion of Pipe Matl.Elbow & Pipe Replaced ML20010G0161981-09-0303 September 1981 LER 81-006/03L-0:on 810706,battery Charger 32 Discovered in Tripped Position.Caused by Faulty delta-P Air Flow Sensing Switch.Switch Replaced ML20010C6171981-08-10010 August 1981 LER 81-018/03L-0:on 810710,during Attempt to Automatically Start,Diesel Generator 21 Shut Down.Caused by Over Crank Due to Incorrectly Set Timer Relays.Relays Reset ML20010B3321981-08-0404 August 1981 LER 81-016/03L-0:on 810705,during Routine Check of Diesel Generator 23,water Found in Crankcase.Caused by Water Leaking from Lube Oil Cooler Into Lube Oil.Leaking Tube Plugged & Oil Changed ML20009H5441981-07-30030 July 1981 LER 81-017/03L-0:on 810630,feed Breaker for 480-volt Bus 5A Opened & Associated Lockout Relay Actuated.Caused by Defective Westinghouse DB-75 Breaker Tripping Device. Device Replaced ML19350E6831981-06-12012 June 1981 LER 81-014/03L-0:on 810517,one Sensing Device Found Not Operating on Level Transmitters LT-940 & LT-941.Caused by Foreign Matl Buildup on Instrument Stalks of Gem Level Transmitters.Matl Removed & Transmitter Tested 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 ML20004E1881981-05-22022 May 1981 LER 81-012/01T-0:on 810511,3/4-inch Swagelok Union in Remote Reactor Head Vent Line Parted During Test to Assure Operability of Low Power Injection/Rhr Check Valves Prior to Restart.Caused by Improper Installation.Valve Closed ML20004F3741981-05-22022 May 1981 LER 81-011/01T-0:on 810508,pits Observed on Exterior Surface of Svc Water Pump Discharge Piping.Caused by External Corrosion,Resulting in Local Areas Below Min Wall Thickness. Areas Sand Blasted,Patch Welded & Repainted 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 1983-08-19 Category:RO) MONTHYEARML20024E7931983-08-19019 August 1983
[Table view]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 ML20024A3841983-05-27027 May 1983 LER 83-015/03L-0:on 830427,shutdown Initiated When Containment Spray Pump 21 Did Not Meet Operability Criteria. Repairs Not Completed within Allowable Time Period.Caused by High Vibrations.Pump replaced.W/830527 Ltr ML20024A3791983-05-22022 May 1983 LER 83-017/03L-0:on 830422,leak Observed in Isolation Valve Seal Water Sys.Caused by Damage to 3/8-inch Stainless Steel Weld Connection FW10016.Weld repaired.W/830522 Ltr ML20024A3831983-05-22022 May 1983 LER 83-021/03L-0:on 830422,analysis Revealed Adsorption Efficiency for Methyl Iodine of 82.2%.Cause Under Investigation.Charcoal Filters replaced.W/830522 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 ML20024A5171983-05-22022 May 1983 LER 83-016/03L-0:on 830422,boron Injection Tank Level Channel 944F Became Inoperable.Caused by Erroneous Level Indication Due to Boric Acid Solidification in Instrument Impulse Line.Affected Impulse Line cleaned.W/830522 Ltr ML20024A5291983-05-22022 May 1983 LER 83-018/03L-0:on 830422,plant Shutdown Commenced When Binding of Valve 1870 Could Not Be Corrected within Tech Spec Time Period.Cause Not Stated.Binding Alleviated by Lubricating Valve Stem & Universal joints.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 ML20024A5241983-05-20020 May 1983 LER 83-013/03L-0:on 830420,during Surveillance Testing of Containment Isolation Valves,Valve 1702 Did Not Fully Close. Cause Not Stated.Shaft & Inside of Actuator Cleaned.Air Motor Diaphragm Replaced as Preventive measure.W/830520 Ltr 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 ML20027B9071982-09-16016 September 1982 LER 82-037/99X-0:on 820902,svc Water Leak Identified on Reactor Containment Fan Cooler Unit 22.Cause Under Investigation.Leakage Will Be Closely Monitored & Failed Tubes Examined During Upcoming Refueling Outage ML20052B8631982-04-19019 April 1982 LER 82-014/03L-0:on 820320,valve 267A Found Leaking.Two Boric Acid Transfer Pumps & Boric Acid Storage Sys Isolated in Order to Isolate Valve for Repairs.Caused by Diaphragm Failure.Valve Repaired ML20050D5251982-03-26026 March 1982 LER 82-008/03L-0:on 820224,during Routine Insp,Three Lines in Rack 15 of Weld Channel & Containment Penetration Sys Were Isolated.Cause Not Stated.Affected Lines Promptly Returned to Svc & Sys Checked to Assure Proper line-ups ML20050C0821982-03-24024 March 1982 LER 82-010/01T-0:on 820310,determined That Existing Operating Procedures Required Necessary Safeguards Equipment to Be Operable Prior to Bringing Reactor Critical But Did Not Establish Specific Requirements in Hot Shutdown 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 ML20050B3141982-03-19019 March 1982 LER 82-007/03L-0:on 820217,during Visual Insp of Number 21 Battery Cell,Number 31 Cell Found Leaking & Exhibiting Low Electrolyte Level.Caused by Cell Casing Crack Due to Expansion of Positive Plates.Cell Replaced 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 ML20042A6831982-03-0909 March 1982 LER 82-006/03L-0:on 820207,power Range Nuclear Instrumentation Channel N 43 Indicated High & Then Became Erratic.Cause Not Given.Channel Returned to Normal During Operation.Instrumentation to Be Closely Monitored ML20042A2461982-03-0808 March 1982 LER 82-005/03L-0:on 820206,main Steam Isolation Valve Dwg 20728-B for Loop 23 Failed to Close During Isolation of Secondary Plant for Maint.Caused by Insufficient Packing Lubrication.Packing Lubricated & Valve Stroked ML20041E2021982-02-24024 February 1982 Updated LER 81-003/03L-1:on 810119,during Surveillance Test PT-R35 Shutoff Valve 822B in Component Cooling Water Return Line 21 for RHR Heat Exchange Would Not Open.Caused by Loose Torque Switch.Switch Tightened 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 ML20041E2061982-02-24024 February 1982 Updated LER 81-004/03L-1:on 810119,during Surveillance Test PT-R35 Opening Time for One of Two Power Operated Relief Valves (PCV-456) Was 2.5-s Longer than Permitted.Caused by Nitrogen Supply Valve Inadvertently Closed.Valve Reopened 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 ML20041B2321982-02-0909 February 1982 LER 82-002/03L-0:on 820110,during Full Power Operation,Weld Channel & Penetration Pressurization Sys Air Consumption Exceeded Tech Spec Limits.Caused by Excessive Seat Leakage in Fischer Valve 1192.Valve Removed & Seat Replaced 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 ML20040E4311982-01-21021 January 1982 LER 81-031/03L-0:on 811223,during Surveillance Test PT-MI/PC-MI at 100% Power,Value for Q (Upper) on Channel N44 Was Found Incorrect.Caused by Transcription Error.Channel Recalibr & Retested Satisfactorily 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 ML20039D9121981-12-21021 December 1981 LER 81-029/03L-0:on 811119,during Test Run of Safety Injection Pump,Motor Emitted Smoke & Did Not Turn.Caused by Frozen Shaft Bushings on Pump Rotating Elements.Pump Replaced ML20039D9081981-12-21021 December 1981 LER 81-028/03L-0:on 811120,pressurizer Safety Valve PCV-464 Found to Actuate Approx 4% Below Tech Spec Min.Cause Unknown.Valve Readjusted & Retested 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 ML20039B5971981-12-10010 December 1981 LER 81-027/03L-0:on 811110,primary Heat Trace Circuit for Balance Leakoff Line of Safety Injection Pump 23 Failed. Caused by Burned & Broken Connection at Chromalox Strip Heater Element for Thrust Balance Line ML20039B1581981-12-10010 December 1981 LER 81-009/03L-0:on 811110,battery Charger 31 Tripped.Cause Not specified.Delta-P Air Flow Sensing Switch Replaced ML20038B8141981-11-24024 November 1981 LER 81-026/03L-0:on 811029,reduction Observed in Delta & Average Temp on Loop 23.Caused by Defect in Hot Leg Model 176JA Resistance Temp Detector Circuit.Resistance Temp Element Replaced 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 ML20010H7531981-09-14014 September 1981 LER 81-021/99X-0:on 810829,pinhole Leak Discovered in Elbow on 2-inch Svc Water Outlet Line.Caused by Erosion of Pipe Matl.Elbow & Pipe Replaced ML20010G0161981-09-0303 September 1981 LER 81-006/03L-0:on 810706,battery Charger 32 Discovered in Tripped Position.Caused by Faulty delta-P Air Flow Sensing Switch.Switch Replaced ML20010C6171981-08-10010 August 1981 LER 81-018/03L-0:on 810710,during Attempt to Automatically Start,Diesel Generator 21 Shut Down.Caused by Over Crank Due to Incorrectly Set Timer Relays.Relays Reset ML20010B3321981-08-0404 August 1981 LER 81-016/03L-0:on 810705,during Routine Check of Diesel Generator 23,water Found in Crankcase.Caused by Water Leaking from Lube Oil Cooler Into Lube Oil.Leaking Tube Plugged & Oil Changed ML20009H5441981-07-30030 July 1981 LER 81-017/03L-0:on 810630,feed Breaker for 480-volt Bus 5A Opened & Associated Lockout Relay Actuated.Caused by Defective Westinghouse DB-75 Breaker Tripping Device. Device Replaced ML19350E6831981-06-12012 June 1981 LER 81-014/03L-0:on 810517,one Sensing Device Found Not Operating on Level Transmitters LT-940 & LT-941.Caused by Foreign Matl Buildup on Instrument Stalks of Gem Level Transmitters.Matl Removed & Transmitter Tested 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 ML20004E1881981-05-22022 May 1981 LER 81-012/01T-0:on 810511,3/4-inch Swagelok Union in Remote Reactor Head Vent Line Parted During Test to Assure Operability of Low Power Injection/Rhr Check Valves Prior to Restart.Caused by Improper Installation.Valve Closed ML20004F3741981-05-22022 May 1981 LER 81-011/01T-0:on 810508,pits Observed on Exterior Surface of Svc Water Pump Discharge Piping.Caused by External Corrosion,Resulting in Local Areas Below Min Wall Thickness. Areas Sand Blasted,Patch Welded & Repainted 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 1983-08-19 Category:TEXT-SAFETY REPORT MONTHYEARML20217H8501999-10-14014 October 1999
[Table view]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 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 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 ML20058K4151990-06-30030 June 1990 Steam Generator Insp,Repair & Restoration Program Presentation to Nrc ML20058K4121990-06-30030 June 1990 Status Rept,Indian Point Unit 2 Mid-Cycle Steam Generator Insp Presentation to Nrc ML20043A4891990-05-30030 May 1990 Nonproprietary Indian Point Unit 2 Steam Generator Insp, Repair & Restoration Program. ML20042F1441989-12-31031 December 1989 New York Power Authority Annual Rept for 1989. W/900430 Ltr 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 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 ML20247N5331989-05-31031 May 1989 Nonproprietary Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage ML20247J8071989-05-31031 May 1989 Containment Margin Improvement Analysis for Indian Point Unit 3 ML20247G5171989-04-30030 April 1989 Monthly Maint Category I Rept Pages from Monthly Operating Rept for Apr 1989 for Indian Point 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 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 ML20248F3001988-12-31031 December 1988 10CFR50.59(b) Rept of Changes,Tests & Experiments Completed in 1988 ML20246E2711988-12-31031 December 1988 Con Edison 1988 Annual Rept 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 ML20154M5691988-07-31031 July 1988 Revised Page to Monthly Operating Rept for Jul 1988 for Indian Point Station Unit 2 ML20151N7881988-07-31031 July 1988 Rev 1 to Charpy Toughness & Brittle Transition Temp Characterization of HAZ High Hardness Zone of Indian Point Unit 2 Steam Generator Girth Weld by Gleeble Weld Thermal Cycle Simulation ML20006B4741988-05-31031 May 1988 Nonproprietary Indian Point Unit 2 Evaluation for Tube Vibration Induced Fatigue. ML20151N7821988-05-31031 May 1988 Fracture Sensitivity Study of Girth Weld 6 Repaired Configuration,Indian Point Unit 2 ML20153F9161988-04-28028 April 1988 Changes,Tests & Experiments - 1986 ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness 1999-02-09 |
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