05000281/LER-1986-020-02, Forwards LER 86-020-02 & Surry Unit 2 Reactor Trip & Feedwater Pipe Failure Rept

From kanterella

(Redirected from ML18150A018)

Jump to navigation Jump to search

Forwards LER 86-020-02 & Surry Unit 2 Reactor Trip & Feedwater Pipe Failure Rept
Person / Time
ML18150A018
Site:	Surry
Issue date:	03/31/1987
From:	Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18150A019	List: 05000281/LER-1986-020-02, Forwards LER 86-020-02 & Surry Unit 2 Reactor Trip & Feedwater Pipe Failure Rept ML18150A021
References
87-057B, 87-57B, NUDOCS 8704130351
Download: ML18150A018 (1)
v • d • e

LER-1986-020, Forwards LER 86-020-02 & Surry Unit 2 Reactor Trip & Feedwater Pipe Failure Rept

Event date:
Report date:
2811986020R02 - NRC Website
v • d • e

text

..

Vepco March 31, 1987 U.S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C.

20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P.O. Box 315 Surry, VA 23883 Serial No:

Docket No.:

License No:

86-057B 50-281 DPR-37 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby submits the following updated Licensee Event Report for Surry Unit 2.

REPORT NUMBER 86-020-02 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.

Very truly yours,

(?/-~~

R. F. Saunders Station Manager

Enclosure cc:

Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323 51 670331 6704130D30C~ 05000281 pDR A

Licensee Event Report

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000280/LER-1986-001-01, :on 860107,reactor Trip Occurred Due to Loss of Instrument Air.Caused by Hot Gas Bypass Valve in Dryer Improperly Adjusted to Maintain Air Temp Above Freezing. Operator Attempted to Gain Manual Control	on 860107,reactor Trip Occurred Due to Loss of Instrument Air.Caused by Hot Gas Bypass Valve in Dryer Improperly Adjusted to Maintain Air Temp Above Freezing. Operator Attempted to Gain Manual Control
05000280/LER-1986-002, :on 860108,unit Tripped from 97% Power & Specific Activity Sample of Reactor Coolant Exceeded Tech Spec Dose Equivalent I-131 Limit.Caused by Iodine Spike. Level Monitored Every 4 H	on 860108,unit Tripped from 97% Power & Specific Activity Sample of Reactor Coolant Exceeded Tech Spec Dose Equivalent I-131 Limit.Caused by Iodine Spike. Level Monitored Every 4 H
05000280/LER-1986-002-01, :on 860119,at 100% Power,Excess Leakage of RCS Noted.Caused by Failed motor-operated Valve Packing & Failed Diesel Generator Diaphragm.Valve Will Be Repacked & Diaphragm Replaced During Next Suitable Outage	on 860119,at 100% Power,Excess Leakage of RCS Noted.Caused by Failed motor-operated Valve Packing & Failed Diesel Generator Diaphragm.Valve Will Be Repacked & Diaphragm Replaced During Next Suitable Outage
05000281/LER-1986-003-03, :on 860216,turbine Tripped Due to High Level in Steam Generator B.Caused When Main Feedwater Bypass Valve B Failed to Close on Demand.Valve Failure Caused by Blockage in Air Pilot Relay.Blockage Dislodged	on 860216,turbine Tripped Due to High Level in Steam Generator B.Caused When Main Feedwater Bypass Valve B Failed to Close on Demand.Valve Failure Caused by Blockage in Air Pilot Relay.Blockage Dislodged
05000280/LER-1986-003, :on 860119,at 97% Power,Reactor Tripped Manually Following Drop of Four Fuel Rods Into Core & Turbine Runback.Caused by Control Rod Logic Cabinet Jump Short.Abnormal Procedure 1.4 Changed	on 860119,at 97% Power,Reactor Tripped Manually Following Drop of Four Fuel Rods Into Core & Turbine Runback.Caused by Control Rod Logic Cabinet Jump Short.Abnormal Procedure 1.4 Changed
05000280/LER-1986-004, :on 860119,following Manual Reactor Trip, Specific Activity Sample of Primary Coolant Sys Exceeded Dose Equivalent I-131 Level of 1.0 Uci/Cc.Caused by Fuel Element Defects in Reactor Core	on 860119,following Manual Reactor Trip, Specific Activity Sample of Primary Coolant Sys Exceeded Dose Equivalent I-131 Level of 1.0 Uci/Cc.Caused by Fuel Element Defects in Reactor Core
05000281/LER-1986-004-02, :on 860219,during Test of Component Cooling Check Valves in RHR Sys,Operator Made Incorrect Valve Lineup Resulting in Isolation Component Cooling Flow to RHR HX a & B.Event Rept Placed in Operator Reading Manual	on 860219,during Test of Component Cooling Check Valves in RHR Sys,Operator Made Incorrect Valve Lineup Resulting in Isolation Component Cooling Flow to RHR HX a & B.Event Rept Placed in Operator Reading Manual
05000281/LER-1986-005-01, :on 860511,overpower Delta T Reactor Trip Occurred When Spurious Rod Signals from Emergency Buses Caused Turbine Runback.Caused by Malfunctioning Auto Load Tap Changer on Transformer.Changer replaced.W/860610 1tr	on 860511,overpower Delta T Reactor Trip Occurred When Spurious Rod Signals from Emergency Buses Caused Turbine Runback.Caused by Malfunctioning Auto Load Tap Changer on Transformer.Changer replaced.W/860610 1tr
05000280/LER-1986-005, :on 860124,unit Manually Tripped from 42% Power Due to Arcing on Isolated Phase Bus Duct A.Caused by Corrosion on Contact Surfaces of Lugs of Ground Straps. Damaged Section of Duct Replaced & Welded	on 860124,unit Manually Tripped from 42% Power Due to Arcing on Isolated Phase Bus Duct A.Caused by Corrosion on Contact Surfaces of Lugs of Ground Straps. Damaged Section of Duct Replaced & Welded
05000280/LER-1986-006, :on 860124,specific Activity Sample of Reactor Coolant Showed Dose Equivalent I-131 Level of 1.22 Mci/Cc After Manual Reactor Trip from 42% Power.Caused by Fuel Element Defects in Core.Level Monitored Every 4 H	on 860124,specific Activity Sample of Reactor Coolant Showed Dose Equivalent I-131 Level of 1.22 Mci/Cc After Manual Reactor Trip from 42% Power.Caused by Fuel Element Defects in Core.Level Monitored Every 4 H
05000281/LER-1986-006-03, :on 860616,svc Water Leak Discovered in Expansion Joint on Svc Water Return Line from Recirculation Spray Hx.Caused by Galvonic Corrosion.Expansion Joints Replaced & Carbon Steel on Joints Coated	on 860616,svc Water Leak Discovered in Expansion Joint on Svc Water Return Line from Recirculation Spray Hx.Caused by Galvonic Corrosion.Expansion Joints Replaced & Carbon Steel on Joints Coated
05000281/LER-1986-007-02, :on 860617,reactor Trip Occurred Due to High Level in Steam Generator A.Caused by Failure of Valve FCV-2478 to Close Due to Metal Debris Between Plug & Valve Seat.Metal Debris Removed & Valve Reassembled	on 860617,reactor Trip Occurred Due to High Level in Steam Generator A.Caused by Failure of Valve FCV-2478 to Close Due to Metal Debris Between Plug & Valve Seat.Metal Debris Removed & Valve Reassembled
05000280/LER-1986-007, :on 860107,two Bolting Studs in Valve Flange MOV-SI-1890B Failed.Caused by Intergranular Stress Corrosion of Bolting Matl.Insp Conducted & Stud Matl Replaced,As Necessary	on 860107,two Bolting Studs in Valve Flange MOV-SI-1890B Failed.Caused by Intergranular Stress Corrosion of Bolting Matl.Insp Conducted & Stud Matl Replaced,As Necessary
05000281/LER-1986-008-03, :on 860706,low Head Safety Injection Pump Discharge Isolation Valve MOV-2890C to Cold Legs Found Energized in Open Position.Human Performance Evaluation Will Be Performed to Determine Cause	on 860706,low Head Safety Injection Pump Discharge Isolation Valve MOV-2890C to Cold Legs Found Energized in Open Position.Human Performance Evaluation Will Be Performed to Determine Cause
05000281/LER-1986-008, :on 860706,low Head Safety Injection Pump Discharge Isolation Valve to Cold Leg Found Energized in Open Position.Cause Undetermined.Procedural Changes Will Be Implemented	on 860706,low Head Safety Injection Pump Discharge Isolation Valve to Cold Leg Found Energized in Open Position.Cause Undetermined.Procedural Changes Will Be Implemented
05000280/LER-1986-008, :on 860213,unexpected Start of Auxiliary Feed Pump 2-FW-P-3B Occurred.Caused by Open Coil in Bfd Relay AFP-3XB.Relay Replaced & Tested Satisfactorily	on 860213,unexpected Start of Auxiliary Feed Pump 2-FW-P-3B Occurred.Caused by Open Coil in Bfd Relay AFP-3XB.Relay Replaced & Tested Satisfactorily
05000280/LER-1986-009, :on 860208,during Startup,Operating Main Feedwater Pump Tripped Due to High Level in Steam Generator C.Caused by Dust Accumulation in Pilot Relay Blocking Air to Valve Operator.Blockage Removed	on 860208,during Startup,Operating Main Feedwater Pump Tripped Due to High Level in Steam Generator C.Caused by Dust Accumulation in Pilot Relay Blocking Air to Valve Operator.Blockage Removed
05000281/LER-1986-009-03, :on 860709,reactor Trip Breaker Opened Following Spurious RCS Low Flow Signal.Caused by Personnel Error During Replacement of Failed Reactor Protection Sys Train B Relay.Individual Counseled	on 860709,reactor Trip Breaker Opened Following Spurious RCS Low Flow Signal.Caused by Personnel Error During Replacement of Failed Reactor Protection Sys Train B Relay.Individual Counseled
05000281/LER-1986-010-02, :on 860711,pump B Discharge Pressure Dropped to Zero,Causing Inoperability of Both Charging Pumps a & B. Caused by Air Introduced in Sys During Maint on Pump A.Pump Vented.Both Pumps Returned to Svc	on 860711,pump B Discharge Pressure Dropped to Zero,Causing Inoperability of Both Charging Pumps a & B. Caused by Air Introduced in Sys During Maint on Pump A.Pump Vented.Both Pumps Returned to Svc
05000280/LER-1986-010, :on 860207,reactor & Turbine Tripped on High Steam Generator Level.Caused by Failure to Adjust Feedback Cam Following Maint.Cam Adjusted & Maint Procedure Revised	on 860207,reactor & Turbine Tripped on High Steam Generator Level.Caused by Failure to Adjust Feedback Cam Following Maint.Cam Adjusted & Maint Procedure Revised
05000281/LER-1986-011-02, :on 860720,determined That Svc Water Leaking Into Containment from Recirculation Spray HX (Rshx).Caused by Leaking Tubes in RSHX B.Tubes Plugged.Rshx Successfully Pressure Tested	on 860720,determined That Svc Water Leaking Into Containment from Recirculation Spray HX (Rshx).Caused by Leaking Tubes in RSHX B.Tubes Plugged.Rshx Successfully Pressure Tested
05000281/LER-1986-012-03, :on 860821,during Monthly Performance Test, Relay LM-REL-200A1 Found Failed & on 860826 Relay R-LM-REL-200A2 Found Failed.Caused by Intermittent Operation of Comparator.Relays Replaced & Tested	on 860821,during Monthly Performance Test, Relay LM-REL-200A1 Found Failed & on 860826 Relay R-LM-REL-200A2 Found Failed.Caused by Intermittent Operation of Comparator.Relays Replaced & Tested
05000280/LER-1986-012, :on 860409,flow Path from Boric Acid Tank to Charging Pump Suction Inadvertently Isolated.Caused by Personnel Error in Isolating Boric Acid Filter.Flow Path Reestablished by Unisolating Filter	on 860409,flow Path from Boric Acid Tank to Charging Pump Suction Inadvertently Isolated.Caused by Personnel Error in Isolating Boric Acid Filter.Flow Path Reestablished by Unisolating Filter
05000281/LER-1986-012-02, :on 860821,during Monthly Performance Test, Relay LM-REL-200A1 Found Failed & on 860826,relay LM-REL-200A2 Found Failed.Caused by Intermittent Operation of Comparator.Relays Replaced & Tested	on 860821,during Monthly Performance Test, Relay LM-REL-200A1 Found Failed & on 860826,relay LM-REL-200A2 Found Failed.Caused by Intermittent Operation of Comparator.Relays Replaced & Tested
05000280/LER-1986-013, :on 860510,following Shutdown for Refueling Outage,Specific Activity Sample of Reactor Coolant Showed Dose Equivalent of I-131 1.05 Mci/Cc.Caused by Fuel Element Defects in Reactor Core.Level Monitored	on 860510,following Shutdown for Refueling Outage,Specific Activity Sample of Reactor Coolant Showed Dose Equivalent of I-131 1.05 Mci/Cc.Caused by Fuel Element Defects in Reactor Core.Level Monitored
05000281/LER-1986-013-02, :on 861005,auxiliary Feedwater Pumps Started & Steam Generator Blowdown Trip Valves Closed.Caused by Cycling of Auxiliary Lube Oil Pump for Main Feed Pump (MFP) & Trip of MFP Breaker.Procedures Changed	on 861005,auxiliary Feedwater Pumps Started & Steam Generator Blowdown Trip Valves Closed.Caused by Cycling of Auxiliary Lube Oil Pump for Main Feed Pump (MFP) & Trip of MFP Breaker.Procedures Changed	10 CFR 50.73(a)(2)(iv), System Actuation
05000280/LER-1986-014, :on 860511,temporary Degradation of Dc Bus Voltage B Experienced,Resulting in ESF Actuation.Caused by Inadequate Procedure in Design Change to Replace Batteries. Procedure Will Be Revised	on 860511,temporary Degradation of Dc Bus Voltage B Experienced,Resulting in ESF Actuation.Caused by Inadequate Procedure in Design Change to Replace Batteries. Procedure Will Be Revised
05000281/LER-1986-014-02, :on 861010,results of Type C Containment Leakage Testing Indicated That Inside & Outside Containment Sump Trip Valves Had Leakage Greater than 300 Scfh.Caused by Erosion of Plug & Seat.Valves Will Be Replaced	on 861010,results of Type C Containment Leakage Testing Indicated That Inside & Outside Containment Sump Trip Valves Had Leakage Greater than 300 Scfh.Caused by Erosion of Plug & Seat.Valves Will Be Replaced
05000281/LER-1986-015-01, :on 861031,pressurizer Safety Valve Setpoints Found Outside Allowable Limits.Caused by Failure to Compensate for Operating Temp & Valve Wear.Valves Replaced & Setpoints Reset	on 861031,pressurizer Safety Valve Setpoints Found Outside Allowable Limits.Caused by Failure to Compensate for Operating Temp & Valve Wear.Valves Replaced & Setpoints Reset	10 CFR 50.73(a)(2)(1)
05000281/LER-1986-015-02, :on 861031,pressurizer Safety Valves Had Lift Setpoints Outside Allowable Limits During Refueling Surveillance Testing.Safety Valve Setpoints Reset.Vendor Failure Analysis Underway	on 861031,pressurizer Safety Valves Had Lift Setpoints Outside Allowable Limits During Refueling Surveillance Testing.Safety Valve Setpoints Reset.Vendor Failure Analysis Underway	10 CFR 50.73(a)(2)(1)
05000280/LER-1986-016, :on 860510,lift Settings for Five Safety Valves on Main Steam Line B Found 3% Greater than Lift Setpoints. Caused by Setpoints Set Too High During 841223 Calibr Due to Unreliable Indication	on 860510,lift Settings for Five Safety Valves on Main Steam Line B Found 3% Greater than Lift Setpoints. Caused by Setpoints Set Too High During 841223 Calibr Due to Unreliable Indication
05000281/LER-1986-016-01, :on 861116,containment Radiation Monitor Trip Valves TV-RM-200A,B & C Closed on Safeguards Signal.Caused by Inadequate Procedure.Procedure Will Be Modified	on 861116,containment Radiation Monitor Trip Valves TV-RM-200A,B & C Closed on Safeguards Signal.Caused by Inadequate Procedure.Procedure Will Be Modified	10 CFR 50.73(a)(2)(iv), System Actuation
05000281/LER-1986-017-02, :on 861121,during Periodic Test 8.5A, Inadvertent Auto Start of Emergency Diesel Generator 3 (EIIS-ER) Occurred.Caused by Personnel Error.Testing Suspended & Diesel Shut Down	on 861121,during Periodic Test 8.5A, Inadvertent Auto Start of Emergency Diesel Generator 3 (EIIS-ER) Occurred.Caused by Personnel Error.Testing Suspended & Diesel Shut Down	10 CFR 50.73(a)(2)
05000280/LER-1986-017, :on 860524,loss of Operating RHR & Component Cooling Pumps 1B Occurred Due to Undervoltage Transient. Caused by Personnel Error.Forced Coolant Circulation Reestablished	on 860524,loss of Operating RHR & Component Cooling Pumps 1B Occurred Due to Undervoltage Transient. Caused by Personnel Error.Forced Coolant Circulation Reestablished
05000281/LER-1986-018-02, :on 861112,environmentally Qualified Components Found Not Installed Per Approved Raychem Guidelines.Caused by Procedures Not Conforming to Raychem Application Guide. Procedures Revised	on 861112,environmentally Qualified Components Found Not Installed Per Approved Raychem Guidelines.Caused by Procedures Not Conforming to Raychem Application Guide. Procedures Revised
05000281/LER-1986-018, :on 861112,discovered Environ Qualified Components Not Installed Per Approved Raychem Guidelines. Caused by Inadequate Training of Personnel Installing Matl. Procedures Revised & Addl Training Conducted	on 861112,discovered Environ Qualified Components Not Installed Per Approved Raychem Guidelines. Caused by Inadequate Training of Personnel Installing Matl. Procedures Revised & Addl Training Conducted
05000280/LER-1986-018, :on 860528,emergency Diesel Generator 3 Automatically Started.Caused by Inadequate Design Change Procedure Causing Interruption of Dc Power.Procedure Revised	on 860528,emergency Diesel Generator 3 Automatically Started.Caused by Inadequate Design Change Procedure Causing Interruption of Dc Power.Procedure Revised
05000281/LER-1986-019-01, :on 861201,individual Rod Position Indicators (Irpi) for Control Rods Out of Calibr.Caused by Instrument Drift.All Inoperable Irpis Recalibr & Returned to Svc	on 861201,individual Rod Position Indicators (Irpi) for Control Rods Out of Calibr.Caused by Instrument Drift.All Inoperable Irpis Recalibr & Returned to Svc
05000280/LER-1986-019, :on 860711,automatic Opening of Reactor Trip Breakers Occurred.Caused by Spurious Turbine First Stage Pressure Spike That Unblocked Permissive P.7	on 860711,automatic Opening of Reactor Trip Breakers Occurred.Caused by Spurious Turbine First Stage Pressure Spike That Unblocked Permissive P.7
05000280/LER-1986-020, :on 860609,during Environ Qualification Insp, Limitorque Motor Valve Operator Wiring Found Questionable. Unidentifiable Wiring Introduced Through Plant Field Changes.Wiring Replaced	on 860609,during Environ Qualification Insp, Limitorque Motor Valve Operator Wiring Found Questionable. Unidentifiable Wiring Introduced Through Plant Field Changes.Wiring Replaced
05000281/LER-1986-020, :on 861209,reactor Tripped Due to Low Water Level in Steam Generator C (EIIS-SG).Caused by Improper Reassembly of Valve Following Maint.Unit Inspected & Tested Prior to Startup	on 861209,reactor Tripped Due to Low Water Level in Steam Generator C (EIIS-SG).Caused by Improper Reassembly of Valve Following Maint.Unit Inspected & Tested Prior to Startup
05000281/LER-1986-020-01, Forwards LER 86-020-01 & Reactor Trip & Feedwater Pipe Failure Rept	Forwards LER 86-020-01 & Reactor Trip & Feedwater Pipe Failure Rept
05000281/LER-1986-020-02, Forwards LER 86-020-02 & Surry Unit 2 Reactor Trip & Feedwater Pipe Failure Rept	Forwards LER 86-020-02 & Surry Unit 2 Reactor Trip & Feedwater Pipe Failure Rept
05000280/LER-1986-021, :on 860713,individual Rod Position Indicators (Irpi) Declared Inoperable,Per Tech Spec 3.12.E.Caused by Instrumentation Drift Affected by Primary Coolant Temp & Control Rod Movement.Irpis Recalibr	on 860713,individual Rod Position Indicators (Irpi) Declared Inoperable,Per Tech Spec 3.12.E.Caused by Instrumentation Drift Affected by Primary Coolant Temp & Control Rod Movement.Irpis Recalibr
05000280/LER-1986-022, :on 860916 & 20,partial Train B ESF Actuations Occurred Due to Reactor Protection Sys Relay Failures.Caused by Coil Failure.Coil Replaced & Relay Reinstalled & Tested	on 860916 & 20,partial Train B ESF Actuations Occurred Due to Reactor Protection Sys Relay Failures.Caused by Coil Failure.Coil Replaced & Relay Reinstalled & Tested
05000280/LER-1986-023-01, :on 860820,containment Sump Trip Valve Found Leaking from Inside Containment Isolation Valve.Caused by Loose Valve Position Indication Arm.Valve Manually Isolated & Screw Set Tightened in Indication Arm	on 860820,containment Sump Trip Valve Found Leaking from Inside Containment Isolation Valve.Caused by Loose Valve Position Indication Arm.Valve Manually Isolated & Screw Set Tightened in Indication Arm
05000280/LER-1986-024, :on 860813 & 14,at 100% Power,Control Room Chillers Failed to Operate.Caused by Clogged Chillers Due to Unfiltered River Water Flowing Through Tubes.Chillers Unclogged & Strainer Returned to Svc	on 860813 & 14,at 100% Power,Control Room Chillers Failed to Operate.Caused by Clogged Chillers Due to Unfiltered River Water Flowing Through Tubes.Chillers Unclogged & Strainer Returned to Svc
05000280/LER-1986-025, :on 860918 & 19,control Rods P-6 & P-10 Dropped Into Core,Respectively & Reactor Manually Tripped.Caused by Failed Stationary Gripper Coil & Loose Female Connector Pin. Parts Replaced & Control Rods Tested	on 860918 & 19,control Rods P-6 & P-10 Dropped Into Core,Respectively & Reactor Manually Tripped.Caused by Failed Stationary Gripper Coil & Loose Female Connector Pin. Parts Replaced & Control Rods Tested
05000280/LER-1986-026, :on 860919,quadrant-to-average-power-tilt Ratio Exceeded 2% Tech Spec Limit.Caused by Dropped Control Rod P-6 Due to Failed Stationary Gripper Coil in CRD Mechanism. Coil Replaced	on 860919,quadrant-to-average-power-tilt Ratio Exceeded 2% Tech Spec Limit.Caused by Dropped Control Rod P-6 Due to Failed Stationary Gripper Coil in CRD Mechanism. Coil Replaced
05000280/LER-1986-027, :on 861009,two of Three Control Room Air Conditioning Chillers Found Inoperable.Caused by One Chiller Out for Maint & Other Inoperable Due to Failed Relay.Failed Relay Jumpered & Replaced	on 861009,two of Three Control Room Air Conditioning Chillers Found Inoperable.Caused by One Chiller Out for Maint & Other Inoperable Due to Failed Relay.Failed Relay Jumpered & Replaced	10 CFR 50.73(a)(2)(i)
... further results

Retrieved from "https://kanterella.com/w/index.php?title=05000281/LER-1986-020-02,_Forwards_LER_86-020-02_%26_Surry_Unit_2_Reactor_Trip_%26_Feedwater_Pipe_Failure_Rept&oldid=4989030"