SVP-00-018, Radioactive Effluent Report for January Through December 1999
SVP-00-026, Changes to Emergency Plan Procedures
05000456/LER-1998-003-07, :on 980906,loss of Offsite Power Event Was Experienced Due to Electrical Fault.Caused by Matl Dislodged by High Winds.Maint Contract Specifications Will Be Revised to Establish Requirements for Housekeeping
05000254/LER-2076-027, Reportable Occurrence of Control Rods for Quad-Cities, Unit 1
05000254/LER-2076-026, Reportable Occurrence of Control Rods for Quad-Cities, Unit 1
05000237/LER-1977-016, For Dresden Unit 2 Regarding an Incident Concerning the Torque Switch on the Limitorque Operator for Recirculation Pump Suction Valve MO-2-202-4B Opened and Prevented the Valve from Closing While Isolating the B Recirc
05000237/LER-1977-006, For Dresden Unit 2 Regarding Discovery That Three Surveillance Intervals Had Been Inadvertently Exceeded During a Routine Monthly Surveillance Audit
05000237/LER-1977-008, For Dresden Unit 2 Regarding Discovery of Main Steam Line Low Pressure Isolation Switch 2-261-30C to Trip at 853 PSI, Which Is Below the Technical Specification Requirement of 855 PSI or Greater
05000237/LER-1977-007, For Dresden Unit 2 Regarding Discovery of IRM 16 to Trip at 122% of Scale and IRM 16s Rod Block Setpoint at 111% Due to Instrument Setpoint Drift
05000237/LER-1977-023, For Dresden Unit 2 Regarding Discovery of the 12% APRM Upscale Rod Block Trip Setting to Be at 12.5% for APRM Channel One Due to Setpoint Drift
05000237/LER-1975-048-01, Letter Enclosing LER 75-048-01 Regarding Current Status of a Long-Term Corrective Action to Prevent Reoccurrence of a Through-Wall Crack in the Drywell-Torus Nitrogen Purge Line 1604-18
05000237/LER-1977-003, For Dresden Unit 2 Regarding Discovery of an APRM Averaging Card Relay Contact Failure
05000237/LER-1977-020, Regarding a Pin-Hole Leak in a Weld Crack on the 3A Moisture Separator Drain Tank Drain Line
05000237/LER-1977-027, Regarding Failure of 46 Control Rod Drives to Fully Insert and Latch at Position 00 Following a Reactor Scram on July 9, 1977
05000237/LER-1977-018, For Dresden Unit 2 Regarding Fluctuation of a Off-Gas Monitor as a Result of Instrument Drift and Low Input
05000237/LER-1977-017, For Dresden Unit 2 Regarding Discovery of the Ball Isolation Valve on E Traversing Incore Probe (TIP) System Guide Tube to Open from the Control Room
05000237/LER-1976-074, For Dresden Unit 2 Regarding a Control Rod J-2 Withdrawal of One Notch and Reactivity Inserted by This Resulted in a Transient Power Increase
05000237/LER-1977-024, For Regarding the Inoperability of the Unit 2/3 Diesel Generator for 25 Minutes on June 30, 1977
05000237/LER-1997-012, Regarding Discovery That the Unit 2/3 Radwaste Floor Drain Surge Tank Sump Had Overflowed Its Designed Containment Boundaries
05000237/LER-1977-013, For Dresden Unit 2 Regarding Discovery of a Leak of Reactor Coolant Inside the Primary Containment
05000237/LER-1977-009, For Dresden Unit 2 Regarding an Attempt to Replace a Burned-Out Indicating Light Bulb for the Feed Breaker to MCC 28-2 Which Tripped the Feed and Indirectly Removed the Normal Supply to RPS Bus B and the Instrument Bus
05000237/LER-1979-017-01, X2 for Dresden, Units 2 and 3 Re Inadequacies Observed in Implementation of Administrative Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection System or Engineered Saf
05000237/LER-1978-003, /03L-0 for Dresden, Unit 2 Re Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems
05000237/LER-1977-055, /03X-1 for Dresden, Units 2 and 3 Re Diesel Generator Auto Start Relays
05000237/LER-1980-039, /03X-1 for Dresden, Unit 2 Re HPCI Inboard Steam Supply Valve Opened and Had a Dual Light Indication
05000237/LER-1980-017, /03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close
05000237/LER-1980-033, /03L-0 for Dresden, Unit 2 Re the Frequency of Water Addition to the Torus Increased. Leak Rate Tests Indicated a Leak in the 2B LPCI Heat Exchanger
05000237/LER-1980-001, /03L-0 for Dresden, Unit 2 Re While Performing Weekly Turbine Control Valve Exercising, the 1/2 Scram on RPS Channel a Received from the Closure of 3 Turbine Control Valve Would Not Reset
05000237/LER-1980-015, /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33A Was Found Inoperable During Routine Operability Surveillance
05000237/LER-1980-049, /03L-0 for Dresden, Unit 2 Re at Completion of Secondary Containment Leak Rate Test the Reactor Building Ventilation Isolation Valve 2A-5742 Would Not Open
05000304/LER-1980-009, /03L-0 for Zion Re Conditions Leading to Operation in a Degraded Mode Permitted by a Limiting Condition for Operation or Plant Shutdown Required by a Limiting Condition for Operation Requires a 30 Day Written Report
05000237/LER-1977-043, /03L-0 for Dresden, Unit 2 Re Drywell Hi Pressure Switch PS2-1501-62A Tripped at 42.9 H20 Increasing Pressure
05000237/LER-1977-059, /03L-0 for Dresden, Unit 2 Re During Normal Operation, Surveillance Program Review Revealed Violation of T.S. 1.0.CC.b Maximum Combined Interval Time by 6.5 Days for HPCI Monthly Valve and Pump Operability
05000237/LER-1980-041, /03L-0 for Dresden, Unit 2 Re Reactor Building Vent and Refueling Floor Rad Monitor Surveillance (DCP 2007-12) Was Performed
05000237/LER-1978-038, /03L-0 for Dresden, Unit 2 Re Temperature Isolation Switch 2-261-18C Initiated a Group I Isolation Signal on Channel a
05000237/LER-1980-016, /01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line
05000237/LER-1978-028, /01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suct
05000237/LER-1978-036, /03L-0 for Dresden, Unit 2 Re a SBGT Failed to Start Upon Auto Initiation from a Spurious Reactor Bldg. Hi Rad Signal
05000237/LER-1976-050, Regarding Discovery of the Diesel Generator Cooling Water Pump Breaker in the Tripped Condition
05000237/LER-1977-044, /03L-0 for Dresden, Unit 2 Re Conditions Leading to Operations in a Degraded Mode Permitted by a Limiting Condition for Operation
05000237/LER-1976-012, Regarding Discovery of the 2A LPCI Pump Breaker to Be Out of Service
05000237/LER-1976-048, Regarding Discovery of the APRM Channel 5 Indication Had Dropped from 54% to 31%
05000237/LER-1977-061, /03L-0 for Dresden, Unit 2 Re Reactor Protection System Instrument Settings Found to Be Less Conservative than Those Established by the Technical Specifications Which Do Not Prevent the Fulfillment of the Functional Requirement
05000237/LER-1980-024, /03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d
05000237/LER-1976-015, Regarding Appearance of Isolation Condenser Pipeway Snubbers 2 and 3 to Be in an Inoperable Condition Due to Loss of Fluid
05000237/LER-1976-064, For Dresden, Unit 2 Re Reportable Occurrence Report Submitted with Technical Specifications, Section 6.6.B. Without Enclosures
05000237/LER-1976-060, Re Discovery of Water Leakage in Diesel Generator Room Led Identification of Small Hole in HPCI Test Return Line at Condensate Storage Tank
05000237/LER-1976-047, Regarding Starting Failure of LPCI Pump 2C for Use in Maintaining Torus Water Temperature Requirements
05000237/LER-1976-004, Regarding Discovery of the Drywell High Pressure Scram Sensor PS-2-1621-B to Be Set 0.07 PSI Beyond the Technical Specification Limit of 2.00 PSI
05000237/LER-1976-055, For Dresden, Units 2 and 3 Re Following Inspection, Post-Maintenance Surveillance Test Was Performed on a Standby Gas Train. Maximum Attainable Flow Was Below the Tech Spec Limit
05000237/LER-1981-011-03, L-0 for Dresden, Unit 2 Re Observed Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems or Engineered S
05000237/LER-1980-008, /03L-0 for Dresden, Unit 2 Re Equipment Operator Discovered Level in the 2/3 Diesel Generator Coolant Water Expansion Head Tank Overflowing Thru the Vent Line
05000237/LER-1976-071, Regarding Discovery That a Number of Surveillance Intervals Had Been Inadvertently Exceeded During the 6 Month Period Following a Tech Spec Revision Which Limited Those Intervals
05000237/LER-1976-002, Regarding an Occurrence of a Reactor Scram on Low Vacuum After Condenser Vacuum Was Broken While Unit Was Down for Maintenance
05000237/LER-1976-061, Re During Testing of HPCI Test Return Line, Which Was Suspected to Be Leaking, Was Found That Contamination Demineralized Water Was in Fact Leaking from the Underground Pipe Into the Storm Sewer
05000237/LER-1978-043, /03L-0 for Dresden, Unit 2 Re During Unit start-up, While Pulling CRDs to Criticality on Sequence a the RWM Malfunctioned Causing Rod Insert and Withdraw Blocks
05000237/LER-1977-001, Regarding Notification from GE That the Maximum Average Planar Linear Heat Generation Rate Absolute Limits May No Longer Be Considered Sufficiently Conservative
05000237/LER-1978-034, /03L-0 for Dresden, Unit 2 Re During Normal Plant Operation Main Steam Line Temperature Isolation Switch 2-261-18A Initiated a Group I Isolation Signal on Channel a
05000237/LER-1976-072, Regarding Discovery of Control Rod Drive J-11 to Uncouple and Overtravel When Withdrawn to Position 48
05000237/LER-1976-041, Regarding Discovery of Pressure Switch Ps 2-263-55C to Actuate at 1072 PSI, or 2 PSI Above the Technical Specification Limit
05000237/LER-1976-067, Regarding a General Electric Recommendation That the Upper Limit for RWM Operation Be Raised to 20% Reactor Power
05000237/LER-1976-026, Regarding Discovery of High Flow Switch DPIS 2-1349A to Actuate at 33.5 H20 Dp Which Is Above the Technical Specification Requirement
05000237/LER-1980-022, /03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125
05000237/LER-1977-048, /01T-0 for Dresden Unit 2 Regarding Indication of Cracking on the CRD Return Line
05000237/LER-1976-062, Re Upon Completion of Routine Diesel Generator Surveillance Testing, Control Switch Was Placed in the Stop Position, Generator Output Subsequently Became Erratic, Generator Voltage Began Oscillating
05000237/LER-1976-069, Regarding Receipt of Notification from GE That the Absolute Maximum Average Planar Linear Heat Generation Rate Limits May No Longer Be Considered Sufficiently Conservative
05000237/LER-1976-042, Regarding Discovery of Pressure Switch Ps 2-263-55A to Actuate at 1072 PSI, Which Is Above the Technical Specification Limit
05000237/LER-1977-041, /03L-0 for Dresden, Unit 2 Re APRM 5 Was Found to Ino on 12 Instead of 11 LPRMs Bypassed as Required by T.S. 3.1.1
05000237/LER-1976-029, Regarding Discovery of the All Rods in Relays Did Not Deenergize When Control Rod Drive 9 Was Withdrawn to O2
05000237/LER-1976-003, Regarding Discovery of B Tip Probe at Position 9557, Which Is Past the Normal In-Shield Position of 9649
05000237/LER-1976-049, Regarding Discovery of Core Spray Outboard Injection Valve Mo 2-1402-24B Lost Open/Closed Indication and Could Not Be Electrically Reopened
05000237/LER-1977-050, /03L-0 for Dresden, Unit 2 Re Local Leak Rate Test of Drywell Personnel Air Lock During Refueling
05000237/LER-1978-046, /03L-0 for Dresden, Unit 2 Re Drywell Inspection Was Made After Observing Increased Leakage Into Equipment and Floor Drain Sumps
05000237/LER-1978-040, /03L-0 for Dresden, Unit 2 Re APRM Channel 4 Rod Block Tripped at 12.5%, Exceeding T.S. Sect 3.2 Limit
05000237/LER-1976-021, Regarding Discovery of an Indication in the Isolation Condenser Sensitized Stainless Steel Safe-End
05000237/LER-1976-052, Regarding Discovery of Drywell High Pressure ECCS Initiation Switch Ps 1632A to Actuate at 2.04 PSI, Which Is Above the Technical Specification Limit
05000237/LER-1978-005, /03L-0 for Dresden Unit 2 Regarding the Receipt of a Torus High/Low Level Alarm as a Result of Torus Level Transmitter Instrument Drift
05000237/LER-1976-051, Regarding Failure of Unit 2/3 Diesel Fire Pump to Start During Routine Surveillance Testing
05000237/LER-1976-005, Regarding Discovery of Isolation Condenser Condensate High Flow DPIS 1349B to Actuate at 33.0 Inches Dp Increasing Which Is Above the Technical Specifications
05000237/LER-1977-038, /03L-0 for Dresden 2 Regarding Discovery of a Packing Leak on MSIV 203-2B Which Degraded the Primary Containment Boundry
05000237/LER-1976-009, Regarding HPCI Steam Supply Valve 2-2301-4 Closing and Failure to Reopen During the Quarterly Timing Test
05000237/LER-1977-051, /03L-0 for Dresden, Units 2 and 3 Re During Surveillance, Diesel Tripped Resulting in Operation of Unit 3 in Degraded Mode Permitted by T.S. 3.9.B.2
05000237/LER-1978-004-01, T-0 for Dresden, Unit 2 Re Improper 125V DC Cable Separation
05000237/LER-1975-052, For Dresden Unit 2 Regarding a Report of Rapid Closure of Unit-2 Main Steam Isolation Valve 203-1C
05000237/LER-1976-057, Re Instrument Trip Point for Isolation Was Found at 115.6 Inches H1O Dp During Routine Monthly Surveillance Testing of Reactor Water Level
05000237/LER-1979-056, Regarding an Occurrence of the Closed Indication Light Bulb Socket Shorting While Replacing the Light Bulb
05000237/LER-1976-044, Regarding Discovery of LPCI Permissive Pressure Switch 2-263-52A to Actuate at 367 PSI, Which Is Above the Technical Specification Limit
05000237/LER-1976-013, Regarding Discovery of Drain Valve 2-4999-74 to Be Blocked Open Mechanically and Electrically Inoperable
05000237/LER-1977-029, Regarding the Control Rod Drives F-5 and H-7 Uncoupling and Overtravelling When Withdrawn to Position 48 Following Testing
05000237/LER-1976-014, Regarding an Occurrence of Valves 2-1601-32A and -32E Exceeding the Individual Penetration Leak Rate Limit of 29.381 Scfh
05000237/LER-1976-020, Regarding HPCI Valve 2-2301-45 Exhibiting Seat Leakage in Excess of the Tech Spec Limit
05000237/LER-1977-036, Regarding Failure of the HPCI Motor Speed Changer to Bring the Turbine Speed Above 2800 RPM
05000237/LER-1978-035, /01T-0 for Dresden, Unit 2 Re During pre-installation Corrosion Inspection of Recently Purchased Spent Fuel Storage Racks, Cracks Through Weld Metal in Aluminum Channel to Base Plate Fillet Welds Were Found in 8 of 18 Racks
05000237/LER-1976-073, Regarding Unit 2/3 Nitrogen Storage Tank Level Dropping to 58 Inches Which Is Below Technical Specification
05000237/LER-1978-045, /03L-0 for Dresden, Unit 2 Re While Performing Monthly Surv. Dis 1400-3, Auto Blow-down Permissive Sw. Ps 2-1430-1466D Tripped at 120 Psig
05000237/LER-1976-030, Regarding a Laboratory Analysis Discovery of the a SBGT Train Iodine Removal Efficiency to Be 94.46 + or - .03 Percent Which Is Below the Permissible Limit
05000237/LER-1975-038, A-00 for Dresden Unit 2 Supplemental Report to Letter Dated June 25, 1975, Entitled Failure of Valve MO-2-1301-2 to Operate
05000237/LER-1976-019, Regarding the Discovery of Loose Retainer Clamp Bolt Keepers on 19 of 20 Jet Pumps
05000237/LER-1977-035, Regarding Failure of HPCI 2-2301-8 Mo Valve to Reopen After Completion of Flow Test Surveillance
05000237/LER-1977-002, Regarding Discovery of APRM Flow-Bias Indication Exceeding 100% on Both Channels a and B
05000237/LER-1977-034, /03L-0 for Dresden 2 Regarding Main Steam Line Isolation Switch 2-261-16D Initiation of a Group I Isolation Signal on Channel B
05000237/LER-1976-022, Regarding Discovery of Smoke Emanating from the ECCS Jockey Pump 1401-2As Control Feeder Breaker at MCC 28-1
05000237/LER-1977-032, Regarding Failure of Motor Operated Suction Valve MO-2-1501-5A to a LPCI to Reopen Remotely from the Control Room
05000237/LER-1976-007, Regarding Discovery of the Drywell-To-Torus Dp Dropping to .95 and Below 1.00
05000237/LER-1977-028, Regarding Discovery of the Water Tight Buckhead Door Which Provides Flood Protection to the Ccsw Vault to Be Open
05000237/LER-1977-042, /03L-0 for Dresden 2 Regarding Discovery of Broken Tack Weld on Jet Pump 4 Outboard Restrainer Clamp Bolt Keeper
05000237/LER-1976-025, Regarding a Failure to Verify Personnel Evacuation from the 613 Level During Control Rod Movements
05000237/LER-1980-046, Regarding a Failure to Receive CRD Volume During a Reactor Scram
05000237/LER-1976-016, Regarding a Discovery of a Through-Wall Crack in the 14-Inch HPCI Sensitized Stainless Steel Safe-End
05000237/LER-1976-024, Regarding Premature Lifting of Sblc Relief Valve 1105-A During the Refueling Outage
05000237/LER-1981-080, /031-0 for Dresden, Unit 2 Re Abnormal Degradation of Systems Other than Those Specified in Item B.1.e Above Designed to Contain Radioactive Material Resulting from the Fission Process
05000237/LER-1977-026, Regarding the Discovery of Pressure Switch PS-263-51A to Activate at 614 PSI
05000237/LER-1976-059, Re Review of Quad-Cities Unusual Event Letter Led to Discovery That Dresdens Standby Gas Treatment System Deviated from Single Failure Criteria That Disabled the SBGT System
05000237/LER-1981-030, /01T-0 for Dresden, Unit 2 Re Operator Noticed the HPCI Steam Line Was Cold and Filled with Water. the HPCI System Was Declared Inoperable
05000237/LER-1977-031, Regarding the Unit 2/3 Make-Up Demineralizer Acid and Caustic Day Tanks Overflowed While Being Filled Simultaneously Due to Operator Error
05000237/LER-1975-051, For Dresden Unit 2 Regarding Report of Unit-2 High Torus Water Level Exceeding the Technical Specifications Limit
05000237/LER-1980-027, /03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator
05000237/LER-1977-039, /03L-0 for Dresden, Unit 2 Re a Gasket Failure Was Found on Torus Drain Flange 313A Which Degraded the Primary Containment Boundary
05000237/LER-1976-045, Regarding Discovery of Sustained High Reactor Pressure Switch 2-263-53C to Actuate 5 PSI Above the Technical Specification Limit
05000237/LER-1978-027, /03L for Dresden, Unit 2 Re a Sample Taken from Radwaste a WST at 1020 After the Tank Was Filled to 88%
05000237/LER-1975-044, A-00 for Dresden Unit 2 Supplemental Report to Letter Dated October 2, 1975, Entitled Unit-2 Diesel Generator Failure to Start
05000237/LER-1975-039, A-00 for Dresden Unit 2, Supplemental Report on Unit 2 Diesel Generator Starting Failures
05000237/LER-1980-043, /03L-0 for Dresden, Unit 2 Re Surveillance Testing of the Condenser Low Vacuum Switches, Pressure Switch 2-503D Was Found to Have a Trip Point of 22.85 Inches Hg
05000237/LER-1978-041, /03L-0 for Dresden, Units 2 and 3 Re While Testing the Diesel Generator to Allow Monthly Inspection of Redundant Diesel the Thermal Overload for the Diesel Cooling Water Pump Tripped
05000237/LER-1977-045, /01T-0 for Dresden, Unit 2 Re While Preforming Leak Rate Testing Procedure Dts 1600-1, Measured Leakage for Reactor Feed Check Valves 2-220-58B&62B Were 1149 and 195 Scfh
05000249/LER-1975-001, For Dresden, Unit 3, Hydraulic Piping Restraint Failure
05000249/LER-1975-005, Regarding Reactor Feed Pump 3C Pump Casing Vent Line Weld Break
05000237/LER-1978-047, /03L-0 for Dresden, Unit 2 Re During Shutdown While Performing Monthly Sblc Tank Boron Concentration Surv., the Volume/Concentration Parameters of Sblc Tank Were Found Outside Tech. Spec. Limits
05000249/LER-1975-013, For Dresden, Unit 3, Excessive Control Rod Scram Times
05000237/LER-1977-058, /01T-0 for Dresden, Unit 2 Re During Refueling Tests Required by LLRT Procedure Dts 1600-1, Torus Air Sample Line Isolation Valves 8501-1A and 1B Had Through Leakage in Excess of Single Valve Ad Penetration Limits
05000237/LER-1978-020, /03X-01 for Dresden, Unit 1 Re Cause of Failure of the Diesel Generator to Start
05000237/LER-1977-037, /03L-0 for Dresden 2 Regarding the Failure of Recirculation Suction Valve 202-4B to Close from Control Room
05000237/LER-1977-004, Regarding Notification from GE That the Maximum Average Planar Linear Heat Regeneration Rate Limits for Dresden 2 and 3 Have Undergone Further Revision, Including Several Reductions
05000237/LER-1981-024, /03L-0 for Dresden, Unit 2 Re While Conducting Routine Review of Surveillance, It Was Found That the Monthly Surveillance Required by Tech. Spec. 4.4.c.1 for Standby Liquid Control Tank Sampling Was Three Days Overdue
05000237/LER-1978-009, /01T-0 for Dresden Unit 2 Regarding an Occurrence of a Conductivity Transient Due to Condensate Demineralizer Resin Introduction Into the Rx Vessel
05000237/LER-1976-068, Regarding Discovery of Control Rod Drive F-5 to Uncouple and Overtravel When Withdrawn to Position 48
05000237/LER-1980-025, /03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1
05000237/LER-1976-011, Regarding an Occurrence of Leakage in Excess of the 29.381 Scfh Limit Through Valve 2-1601-56
05000237/LER-1977-056, /03X-2 for Dresden, Unit 2 Re While Unit Was Shut Down for Refueling, Service Water Samples Were Taken at All Containment Cooling Heat Exchangers
05000249/LER-1975-016, For Dresden, Unit 3, Excessive Control Rod Scram Times
05000237/LER-1980-002, /03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close
05000237/LER-1976-023, Regarding an Occurrence of Seven of Nine Penetrations Failed a Surveillance Test by Exhibiting Leakage
05000249/LER-1975-004, For Dresden, Unit 3, Reactor Feed Pump Minimum Flow Line Leak
05000237/LER-1981-007, /03L for Dresden, Unit 2 Re While Conducting Steam Line Area Temperature Switch Calibration Surveillance, Temperature Switch TS 2-261-180 Failed to Trip
05000249/LER-1974-025, Regarding Failure of B TIP Machine Valve to Close
05000237/LER-1977-057, /01T-0 for Dresden, Unit 2 Re While in Refuel Mode During Refueling, CRD D-2 Select Switch Allowed Two Drives to Be Simultaneously Selected Defeating the Refuel Mode one-rod-permissive, Contrary to T.S. 3.10.D.1
05000237/LER-1977-054, /01T-0 for Dresden 3 Regarding an Incident Where Unit 2 Was Shut Down for Refueling and Unit 3 at Steady-State Operation, Operability Surveillance Was Performed on Unit 3 Diesel Generator Following Unit 2/3 Diesel Generator Coo
05000237/LER-1974-028, Regarding TIP Machine Ball Valve Failure
05000237/LER-1978-026-03, Re While Performing LPCI Both Indicating Lights Went Out and the Motor Stopped
05000249/LER-1974-027, Regarding Loss of Core Spray 3A Discharge Pressure
05000237/LER-1977-047, /01T-0 for Dresden, Unit 2 Re During Refuel Outage 3 Cracks Were Found on CRD Return Nozzle Thermal Sleeve
05000237/LER-1976-028, Regarding the Discovery That CRD 26-35 Exhibited a Continuous Backlight Irrespective of Rod Position
05000237/LER-1978-025-03, Re While Preforming LPCI and Ccsw Surveillance on Unit 3 Prior to Taking the U-3 D/G Out of Service, a Spike Was Found on the Liquid Process Radiation Monitor for the Service Water Discharge
05000249/LER-1975-007, For Dresden, Unit 3, Failure of Hydraulic Pipe Suppressor
05000237/LER-1976-027, Regarding the Discovery of Sblc Relief Valve 1105-B to Lift at 1380 PSIG Which Is Below the Permissible Range
05000237/LER-1976-032, Regarding Malfunction of the Drive Brakes on the Unit 2/3 Reactor Building Crane Special Slow Speed Hoist
05000249/LER-1974-047, Regarding Failure of Pressure Switch Instrument Taps on 2/3 Radwaste Filter
05000237/LER-1977-046, /03L-0 for Dresden, Unit 2 Re Two Snubbers 26 and 28 Drywell Were Found to Have Less than the Required Amount for Fluid, Thus Questioning Their Operability
05000237/LER-1977-010, Updated LER 77-010-00 for Dresden Unit 3 Regarding Routine Calibration Checks, Undervoltage Relays for Buses 34-1 and 38 Were Found to Be Apparently Inoperative
05000237/LER-1974-033, Regarding Discovery of a Pinhole Leak on the 3A Reactor Feed Pump Minimum Flow Line
05000237/LER-1976-033, Regarding the Threaded Connection (Union) Between the Valve and the Instrument Piping Was Found to Be Leaking on Isolation Condenser Steamline Flow Sensor Instrument
05000237/LER-1978-025, /03L-0 for Dresden Unit 3 Regarding Discovery of a Spike on the Liquid Process Radiation Monitor for the Service Water Discharge
05000237/LER-1977-019, Updated LER 77-019-00 for Dresden Unit 3 Regarding on 06/06/1977, During Routine Half Core Control Rod Drive (CRD) Scram Testing at 46% Power, CRD H-9 (Core Location 30-35) Was Responding Irregularly
05000237/LER-1976-018, Regarding Discovery of Feedwater Isolation Check Valves 2-220-58B and -62B to Exceed the 29.381 Scfh Technical Specification Limit
05000249/LER-1974-029, Letter Submitting Follow-Up Report to Letter Dated 10/02/1974, Entitled: Through-Wall Crack on Torus/Drywell Purge Line, Unit 3
05000237/LER-1974-034, Regarding Failure of a Air Ejector Rupture Disc
05000237/LER-1974-036, Regarding Discovery of a Small Leak on Reactor Feed Pump 3A Minimum Flow Line 3-3205A
05000237/LER-1977-021, /03X-1 for Dresden 3 Regarding a Pin Hole Leak Found in Minimum Flow Line from 3A Reactor Feedwater Pump (Line 3-3205C-6)
05000237/LER-1976-001, Regarding Receipt of Oscillograph Alarms on the 138KV Yard and Observance of Ocb Bus 1 Disconnect to Be Arcing and Glowing
05000237/LER-1975-049, Regarding Failure of Channel a Floor Radiation Monitor Downscale
05000237/LER-1978-031, /03L-0 for Dresden, Unit 2 Re PS-2-1430-1466C Failed to Operate
05000249/LER-1974-054, For Dresden 3 Regarding Core Spray Valve 3-1402-38As Failure to Close
05000237/LER-1976-058, Re During Pump Operability Testing, Core Spray System Test Valve Failed to Close Against Pump Pressure
05000237/LER-1977-022, Regarding an In-Leakage Occurrence, Where Water Was Observed at the 6 Pip Penetration Weld to the Discharge Silencer of the Pump and a Crack Was Noted
05000249/LER-1975-009, For Dresden, Unit 3, 2A MSIV Not Full Open Scram
05000237/LER-1975-046, Regarding Inoperability of Snubber 25
05000249/LER-1975-042, Regarding Failure of LPCI Valve 3-1501-5D Motor Trip
05000237/LER-1974-029, For Dresden 3 Regarding a Through-Wall Crack on Torus/Drywell Purge Line
05000237/LER-1978-029-03, Re Safety Implications Were Minimal Because 1 or More Operable APRMs Per Channel Remained Available as Required by TS 3.2
05000237/LER-1976-070, Regarding the Diesel Generator Failure to Accept a Loading Greater than 2000 Kw
05000237/LER-1980-023, /03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches
05000237/LER-1976-017, Regarding an Occurrence of Standby Liquid Control Isolation Check Valve 2-1101-16 Exceeding the 29.381 Scfh Limit
05000249/LER-1974-037, Regarding the Torus Oxygen Containment Out of Limit
05000237/LER-1978-045-03, Re Auto Blowdown Permissive Sw. Ps 2-1430-1466D Tripped at 120 Psig
05000237/LER-1978-042, /03L-0 for Dresden, Unit 2 Re During Weekly Turbine Control Vlv Exercising 3 Control Vlv Failed to Fast Close at the 10% Vlv Position
05000249/LER-1974-022, Regarding HPCI High Flow Setpoint DPIS 3-2352 of 283 Inches H20 Which Is Above Technical Specifications
05000237/LER-1976-010, Regarding Observation of a Leakage Rate of 167 Scfh for the Volume Bounded by Air-Operated Valves 1601-23, -24, -60, -61, -62, and -63
05000237/LER-1977-011, For Dresden, Units 2 and 3 During Initial Start Attempt, Unit-2/3 Diesel Apparently Turned Over for Approximately 4 Seconds Before Shutting Down
05000249/LER-1975-035, Regarding Failure of Circuit Breaker 152-3403 to Open During a Breaker Trip Event
05000237/LER-1978-032, /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33E & F Were Found Inoperable During Routine Operability Surveillance
05000237/LER-1974-035, For Dresden Units 2 and 3 Regarding Secondary Containment Blowout Panel Failure
05000249/LER-1977-003, For Dresden Unit 3 During Normal Operation, APRM 6 Indication Appeared to Be Registering Power Level Fluctuations of 6 - 10%
05000249/LER-1975-019, For Dresden Unit 3 Regarding a Broken Test Line on Penetration X-105 D
05000249/LER-1977-014, Regarding an Occurrence of the Differential Pressure (D/P) Across the Off Gas High Efficiency Particulate After Filters (HEPA) Increasing to Approximately 13-Inches of Water
05000249/LER-1977-015, Regarding a Pressure Switch 3-1349B Setting Greater than the Tech Specification Limit of Less than or Equal to 32 W.C.D.P
05000249/LER-1975-014, For Dresden, Units 3, Diesel Generator Inoperable
05000249/LER-1977-019, Regarding CRD H-9 Being Determined to Exhibit a 90% Insertion Scram Time in Excess of 7.0 Seconds
05000249/LER-1977-012-01, Regarding a Failure of the Responsible Radman to Collect the Required 4 Hour Reactor Water Sample During the Start-Up
05000249/LER-1975-044, Letter Submitting Correction to Abnormal Occurrence Report Entitled, Off-Gas Increase on Unit 3 (Report 50-249/75/44)
05000249/LER-1974-031, For Dresden Unit 3 Regarding the 2/3 Core Height Water Level Sensors Lits 3-263-73 A&B Having Setpoints Above the Technical Specification Limit
05000237/LER-1979-052, Regarding an Incident Where Fire Water Accumulated on the Mezzanine Floor Which Then Ran Down Into the U2 D/G Control Cabinet Via the D/G Room Vent Ductwork, Causing the Diesel Auto Start Block Alarm
05000249/LER-1977-022, Regarding Water Observed at the 6 Pipe Penetration Weld to the Discharge Silencer of the Pump and a Crack Was Noted
05000237/LER-1980-042, /03L-0 for Dresden, Units 2 and 3 Re That Technical Staff Personnel Revealed That the Ultrasonic Testing of the Scram Discharge Volume Was Not Performed During the 1500-2300 Shift
05000249/LER-1977-032, Regarding a Surveillance Interval Discrepancy for the LPCI and Core Spray Pump and Valve Operability
05000237/LER-1977-053, /03L-0 for Dresden Regarding an Occurrence Where the D/G Overload Alarm Was Received During an Operability Surveillance
05000249/LER-1977-040, /03L-0 for Dresden 3 Regarding the Circuit Breaker for Service Water Makeup Valve MO-3-4102 to the Isolation Condenser Found in Off Position
05000237/LER-1979-064, Regarding Discovery of Torus to Drywell Vacuum Breaker 2-1601-32F to Be Inoperable During Routine Operability Surveillance
05000249/LER-1976-036, For Dresden Unit 3 a Routine Monthly Surveillance Audit Revealed That Three Unit-3 Surveillance Intervals Had Been Inadvertently Exceeded
05000249/LER-1977-052, /03L-0 for Dresden 3 Regarding Discovery of DPIS 3-1349A Tripping at a Level Exceeding the Technical Specification Limit
05000249/LER-1977-048, /03L-0 for Dresden 3 Regarding Excessive Leakage Noted Into the Drywell Floor Drains and a Reactor Shutdown Began in Order to Prevent Exceeding the Tech Specification Limit
05000237/LER-1981-015, /03L-0 for Dresden, Unit 2 Re the Fire Marshall Discovered That the Heat Detectors Were Not Functionally Tested within the 6 Month Interval Required by Tech. Spec. 4.12.A.1
05000249/LER-1977-039, /03L-0 for Dresden 3 Regarding Setpoint for Reactor Level Switch LIS 3-263-57B Found to Be Above the Technical Specification Limit
05000249/LER-1978-003, /01T-0 for Dresden 3 Regarding Discovery of Containment Valve Leakages in Excess of Technical Specification 4.7.A Limits
05000249/LER-1977-001, For Dresden Unit 3 Regarding During Normal Operation, Differential Pressure Indicating Switch 3-1349A Failed in the Opening Position
05000249/LER-1977-016, For Dresden Unit 3 Regarding an Occurrence Where the APRM Flow Bias Off-Normal Alarm Annunciated During Normal Operation
05000249/LER-1977-017, Regarding the Discovery of APRM 4 to Generate an Inop When 60% of the LPRM Inputs Were Bypassed
05000237/LER-1980-050, /03L-0 for Dresden, Unit 2 Re the 1501-62D Pressure Switch Actuated at 44.2 Inches of Water Increasing, Tech. Spec. Limit Is Less than or Equal to 41.6 Inches of Water Increasing
05000237/LER-1980-036, /03L-0 for Dresden, Unit 2 Re Discovery That the Six Month Functional Test Required by Tech. Spec. 4.12.A.1 of the Cardox System Heat Detectors Was Not Performed within the Allowable Surveillance Interval
05000249/LER-1977-011, Regarding Reactor Building Vacuum Breaker A03-1601-20A Not Opening as Required During a Routine Surveillance
05000249/LER-1977-037, For Dresden Unit 3 Regarding an Occurrence of Less than 50% LPRM Inputs in APRM 1 and 2
05000249/LER-1977-021, Regarding the Discovery of a Pin Hole Leak in the Minimum Flow Line from the 3A Reactor Feedwater Pump During a Reactor Shutdown
05000249/LER-1977-012, Regarding a Reactor Water Sampling Interval Violation on April 29, 1977
05000249/LER-1977-025, LERs 77-025-00, 77-026-00, 77-027-00 for Dresden Unit 3 Regarding Electromagnetic Relief Valves 3-203-3C and 3D, the Failure of 3D Electromatic Relief Valve, and the Failure of Electromatics 203-3D and 3E
05000249/LER-1978-009, /01T-0 for Dresden 3 Regarding an Ultrasonic Inspection of the Safe End-To-Pipe Weld on the CRD Return Line Revealed Indications Which Suggested Cracking
05000237/LER-1974-032, Regarding High Pressure Coolant Injection High Flow Instrument Anomaly
05000249/LER-1978-014, /01T-0 for Dresden 3 Regarding 24/48 Vdc Battery Failure to Pass the Refueling Outage Discharge Test
05000237/LER-1975-008, For Dresden, Unit 2 Isolation Level Switch Setpoint Drift
05000249/LER-1980-011, /03L-0 for Dresden Unit 3 Regarding Temperature Switch TS 3-261-17B Tripping at 203.1 Degrees Fahrenheit Which Is Above the Technical Specification
05000249/LER-1978-020, /03L-0 for Dresden 3 Regarding Discovery of Ps 3-203-3C Tripped at 1148 PSI Rx Pressure Incr
05000249/LER-1978-018, /03L-0 for Dresden 3 Regarding the Discovery of U3 Diesel Oil Storage Tank at 9000 Gal. Which Is Below the 10000 Gal. Limit Required by Technical Specification 3.9.c
05000249/LER-1978-011, /01T-0 for Dresden 3 Regarding Cracks Identified in Cladding of CRD Nozzle Inner Radius and Vessel Wall Beneath Nozzle
05000249/LER-1978-002, /03L-0 for Dresden 3 Regarding the Failure of MO-3-1501-5C to Reopen While Performing DOS 1500-1. the Motor Oper. Suction Valve to C LPCI Pp. Closed But Could Not Be Reopened from Control Room
05000249/LER-1979-030, /03X-1 for Dresden Unit 3 Regarding a Supplement to LER 79-30/03L-0 Addressing the Cause and Corrective Actions for the Loss of Position Indication for CRD H-9
05000249/LER-1977-057, /03L-0 for Dresden 3 Regarding the Failure of the LPCI Heat Exchange Discharge Valve (M03-1501-3A) to Open
05000249/LER-1977-038, Regarding a Discovery of the Breaker for the Diesel Generator Cooling Water Pump Tripped
05000237/LER-1979-061, /03L-0 for Dresden, Unit 2 Re Conditions Leading to Operation in a Degraded Mode Permitted by a Limiting Condition for Operation or Plant Shutdown Required by a Limiting Condition for Operation
05000249/LER-1977-043, /03L-0 for Dresden 3 Regarding B Main Steam Line Radiation Monitor Indication Doubling
05000249/LER-1978-028-03, Re While Performing Surv. Dis 250-1, MSL Hi Flow Isolation Sw. Dpis 3-261-2c Tripped at 117 Psid
05000249/LER-1980-017, /03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start
05000249/LER-1980-012, /03L-0 for Dresden Unit 3 Regarding Fuel Pool Area ARM Channels a and B Tripping at Levels Exceeding the Technical Specification
05000249/LER-1978-010, /01T-0 for Dresden 3 Regarding Discovery of 6 Hydraulic Snubbers Nos. 18, 19, 20, and 33 in Unit 3 Drywell and Nos. 1 and 3 in Isolation Condenser Pipeway with Less than Required Amount of Fluid
05000249/LER-1977-041, /01T-0 for Dresden 3 Regarding Discovery of APRM Nos. 4 and 6 to Inop on 12 Instead of 11 LPRMs Bypassed as Required by Technical Specification Section 3.1, Table 3.1.1
05000249/LER-1980-040, /01T-0 for Dresden Unit 3 Regarding Failure of the HPCI Inboard Steam Supply Valve to Open
05000249/LER-1978-016, /03L-0 for Dresden 3 Regarding Leakage Through Standby Liquid Control Check Valve 3-1101-15 Exceeding the T.S.4.7.A Limit for Single Valve Leakage of 29.38 Scfh
05000249/LER-1978-024, /03L-0 for Dresden Unit 3 Regarding the Discovery of PS3-263-53A to Trip at 1178 PSI Which Is Above Technical Specifications
05000249/LER-1978-017, /01T-0 for Dresden 3 Regarding an NRC Request That Immediate Action Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction Va
05000249/LER-1977-036, Regarding a Failure of Test Valve MO-3-1501-20B Located on the Torus Test Return Line to Open
05000249/LER-1980-030, /03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds
05000249/LER-1980-013, /03L-0 for Dresden Unit 3 Regarding B Feedwater Outboard Check Valve 3-220-62B Leakage Exceeding Limit for a Single Isolation Valve
05000237/LER-1977-049, /01T-0 for Dresden, Unit 2 Re Discovery During Plant Life of Conditions Not Specifically Considered in the Safety Analysis Report or Technical Specifications That Require Corrective Measures to Prevent the Existence of Unsafe C
05000249/LER-1978-019, /03L-0 for Dresden 3 Regarding the Discovery of Ps 504C and 504D Found to Trip at 403 PSI and 405 PSI Respectively
05000249/LER-1978-013, /01T-0 for Dresden 3 Regarding Setpoints Being Set High by 10% During the Quarterly Scheduled Calibration Dis 1700-1
05000249/LER-1978-012, /01T-0 for Dresden 3 Regarding Disclosure of One Apparent Crack-Like Indication on the 330 Degrees Feedwater Sparger Along with Several Indications on the CRD Nozzle Thermal Sleeve Retainer
05000249/LER-1980-015, /01T-0 for Dresden Unit 3 Regarding Discovery of Reactor Water Cleanup Mechanical Snubber Fully Retracted
05000249/LER-1978-007, /03L-0 for Dresden 3 Regarding Dis 2300-6 HPCI Area Temperature SW 2371 a Tripped at 284.3 Degrees Fahrenheit
05000249/LER-1977-034, Regarding an Interruption in the Feedwater Flow Signal to the Circulation System
05000249/LER-1978-005, /03L-0 for Dresden 3 Regarding the Discovery of a Pin Hole Leak in Minimum Flow Line from 3B Reactor Feedwater Pump Line 3-3205B-6
05000249/LER-1977-050, /03L-0 for Dresden 3 Regarding an Attempt to Switch Cleanup Pumps and Subsequent System Isolated on High Pressure, and Valve M03-1201-1 Lost All Indication
05000249/LER-1978-006, /03L-0 for Dresden 3 Regarding the Discovery of Vacuum Breaker 1601-32F Binding
05000249/LER-1977-018, Regarding the Discovery of the Analysis Completion Date for the April 77 Dresden 3 Reactor Water Exceeded the Allowable Limit by 17 Hours
05000249/LER-1980-021, /01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operabil
05000249/LER-1980-010, /03L-0 for Dresden Unit 3 Regarding Relief Valves Rv 1105A and 1105B Actuating at 1525 and 1520 PSIG Respectively
05000249/LER-1977-051, /03L-0 for Dresden 3 Regarding Dis 500-2 Setpoint for Reactor Level Switch LIS 3-263-58B Found at ll6.8 Water Dp Which Is Above the Technical Specification Limit
05000249/LER-1977-033, Regarding an Occurrence Where APRM 4 Would Not Generate an Inop Until 13 LPRMs Were Bypassed
05000249/LER-1978-023, /01T-0 for Dresden Unit 3 Regarding Source Range Monitors 24 and 21 Being Declared Inoperable on 05/20/1978
05000249/LER-1979-035, /03L-0 for Dresden Unit 3 Regarding Discovery of Valve Mo 3-1501-3A Having No Position Indication
05000249/LER-1978-022, /03L-0 for Dresden Unit 3 Regarding Discovery of High Flow Isolation Switches DPIS 261-2C, 261-2N, and 261-2S to Trip at Values Exceeding the Technical Specification Limit
05000249/LER-1978-001, /03L-0 for Dresden 3 Regarding the Discovery IRM Nos. 15 and 16 to Trip at 109%
05000249/LER-1980-032, /03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block
05000249/LER-1978-015, /03L-0 for Dresden 3 Regarding Discovery of One Snubber in Drywell to Be Functionally Inoperable by Bench Test During Inspection to Check 10% of All Hydraulic Snubbers During Refueling
NUREG-1582, Forwards Draft Vols 4 & 5 & Apps of NUREG/CR-1582 Re Seismic Hazard Analysis.Repts Served as Theoretical Basis for Development of site-specific Ground Response Spectra for Eastern Us SEP Plants in