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 Issue dateTitleTopic
05000311/LER-1981-089, Supplemental LER 81-089/03X-1:on 810817,during Routine Wear & Alignment Check,Auxiliary Feedwater Pump 23 Linkage Between Trip Mechanism & Valve Found Loose.Caused by Loose Bolts.Bolts Tightened3 November 1982Supplemental LER 81-089/03X-1:on 810817,during Routine Wear & Alignment Check,Auxiliary Feedwater Pump 23 Linkage Between Trip Mechanism & Valve Found Loose.Caused by Loose Bolts.Bolts Tightened
05000311/LER-1982-001, Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed11 November 1983Supplemental LER 82-001/03X-1:on 820110,steam Generator 24 Pressure Channel 4 Failed High.Caused by Ventilation Damper Stuck Open,Freezing Pressure Sensing Line.Damper Freed, Exercised & Closed
05000311/LER-1982-002, Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Vo20 October 1982Supplemental LER 82-002/03X-1:on 820111,battery Charger 2A1 Tripped.Charger Tripped Again Upon Resetting Breaker.Caused by Difference Between Battery & Battery Charger Voltages. Operating Instructions Revised to Adjust Float Voltage
05000311/LER-1982-015, Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor Trip8 December 1982Supplemental LER 82-015/03X-1:on 820221,discovered That Reactor Coolant Leak Rate Surveillance 4.4.7.2.d Due 820220 Not Performed Because Plant Had Not Been in steady-state Condition Due to 820219 Reactor TripMissed surveillance
05000311/LER-1982-017, Supplemental LER 82-017/03X-1:on 820228,svc Water Flow Indicated Zero Upon Starting Containment Fan Coil Unit 22 (Cfcu).On 820301,svc Water Flow to Cfcu 23 Less than Required 2,500 Gpm.Caused by Stuck Valve17 November 1983Supplemental LER 82-017/03X-1:on 820228,svc Water Flow Indicated Zero Upon Starting Containment Fan Coil Unit 22 (Cfcu).On 820301,svc Water Flow to Cfcu 23 Less than Required 2,500 Gpm.Caused by Stuck Valve
05000311/LER-1982-01831 March 1982LER 82-018/03L-0:on 820304,steam Generator 24 Feedwater Channel 2 Flow Indicator Failed.Caused by Failure of Force Motor in Flow Transmitter.Transmitter Properly Repaired, Calibr & Returned to Svc
05000311/LER-1982-01931 March 1982LER 82-019/03L-0:on 820307,undervoltage Condition in Safeguards Equipment Control Cabinet Caused Mod 1 2A Sec Actuation.Caused by Failure of Card File Assembly.Card File Assembly Replaced & Loads Secured.Sys Returned to Svc
05000311/LER-1982-024, Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid Added29 June 1983Supplemental LER 82-024/03X-1:on 820328,sample Results from Boric Acid Storage Tank 21 & Boron Injection Tank 22 Indicated Concentrations Below Tech Spec Limit.Cause Unknown.Boric Acid AddedBoric Acid
Shutdown Margin
05000311/LER-1982-027, Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State20 October 1982Supplemental LER 82-027/03X-1:on 820418,RCS Water Inventory SP(o)4.4.7.2.d Not Performed within Required Time Interval. License Change Request 82-14 Submitted to Eliminate RCS Water Inventory Requirement During Nonsteady State
05000311/LER-1982-070, Supplemental LER 82-070/01X-1:on 830809,0.5 Gpm Svc Water Leak Observed on Containment Fan Coil 24.Caused by Failed Cooling Coil Resulting from Silt Erosion by Particles in Svc Water29 June 1983Supplemental LER 82-070/01X-1:on 830809,0.5 Gpm Svc Water Leak Observed on Containment Fan Coil 24.Caused by Failed Cooling Coil Resulting from Silt Erosion by Particles in Svc WaterPacking leak
05000311/LER-1982-072, Supplemental LER 82-072/03X-1:on 820820,during Surveillance Testing,Discovered That Reactor Trip Breaker B Would Not Trip.Caused by Binding of Undervoltage Coil Solenoid.Coil Replaced & Breaker Reinstalled20 October 1982Supplemental LER 82-072/03X-1:on 820820,during Surveillance Testing,Discovered That Reactor Trip Breaker B Would Not Trip.Caused by Binding of Undervoltage Coil Solenoid.Coil Replaced & Breaker Reinstalled
05000311/LER-1982-074, Corrected LER 82-074/01T-0:on 820813,control Operator Discovered Increased Leakage to Containment Sump.Caused by Coil Failures Due to Silt Particles in Svc Water.Leak Repaired by Blanking Flanges18 August 1982Corrected LER 82-074/01T-0:on 820813,control Operator Discovered Increased Leakage to Containment Sump.Caused by Coil Failures Due to Silt Particles in Svc Water.Leak Repaired by Blanking Flanges
05000311/LER-1982-077, Supplemental LER 82-077/01X-1:on 820818,leakage Discovered from Containment Fan Coil 21.Caused by Erosion of Copper Nickel Piping.Cooling Coils Replaced w/erosion-resistant Matl29 June 1983Supplemental LER 82-077/01X-1:on 820818,leakage Discovered from Containment Fan Coil 21.Caused by Erosion of Copper Nickel Piping.Cooling Coils Replaced w/erosion-resistant Matl
05000311/LER-1982-083, Supplemental LER 82-083/03X-1:on 820812,during Routine Surveillance,Control Room Operator Received Low Svc Water Flow Indication on Containment Fan Coil Unit (Cfcu) 25. Caused by Oysters or Silt Restricting Cfcu Flow20 April 1983Supplemental LER 82-083/03X-1:on 820812,during Routine Surveillance,Control Room Operator Received Low Svc Water Flow Indication on Containment Fan Coil Unit (Cfcu) 25. Caused by Oysters or Silt Restricting Cfcu Flow
05000311/LER-1982-084, Telecopy Message of LER 82-084/01P:on 820829,svc Water Leak on Containment Fan Coil Unit 23 Discovered.Leak Isolated.No Cause Stated.Investigation in Progress30 August 1982Telecopy Message of LER 82-084/01P:on 820829,svc Water Leak on Containment Fan Coil Unit 23 Discovered.Leak Isolated.No Cause Stated.Investigation in Progress
05000311/LER-1982-092, Supplemental LER 82-092/01X-1:on 820908,svc Water Leak Discovered on Containment Fan Coil Unit 21,rendering Unit Inoperable.Caused by Motor Cooler Erosion Due to Silt in Svc Water.Cooler Replaced29 June 1983Supplemental LER 82-092/01X-1:on 820908,svc Water Leak Discovered on Containment Fan Coil Unit 21,rendering Unit Inoperable.Caused by Motor Cooler Erosion Due to Silt in Svc Water.Cooler Replaced
05000311/LER-1982-111, Telecopy Message of LER 82-111/01P:on 821002,during Routine Power Operation,Svc Water Leak Discovered Inside Containment Bldg on Containment Fan Coil Unit 23.Cause Undetermined.Rept Will Be Submitted Per IE Bulletin 80-244 October 1982Telecopy Message of LER 82-111/01P:on 821002,during Routine Power Operation,Svc Water Leak Discovered Inside Containment Bldg on Containment Fan Coil Unit 23.Cause Undetermined.Rept Will Be Submitted Per IE Bulletin 80-24
05000311/LER-1982-141, Updated LER 82-141/03X-1:on 821121 & 1204,P-250 Computer Inoperable Due to Parity Error.Caused by Periodic Increases in Ambient Temp Due to Insufficient Ventilation.Computer Reprogrammed & Action Statement Terminated16 December 1983Updated LER 82-141/03X-1:on 821121 & 1204,P-250 Computer Inoperable Due to Parity Error.Caused by Periodic Increases in Ambient Temp Due to Insufficient Ventilation.Computer Reprogrammed & Action Statement Terminated
05000311/LER-1983-007, Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days18 February 1983Telecopy Message of LER 83-007/01P:on 830218,two 1,000-kip Steam Generator Snubbers Failed to Meet Lockup & Bleed Rate Velocity Requirements.Cause Not Stated.Investigation Continuing.Detailed Rept to Be Submitted in 14 Days
05000311/LER-1983-017, Supplemental LER 83-017/03X-1:on 810515,during Startup & Cycle 1 Operations,Leakage Past Pressurizer PORVs & Pressurizer Overpressure Protection Sys Values Observed. Cause Not Stated.Porvs Modified16 September 1983Supplemental LER 83-017/03X-1:on 810515,during Startup & Cycle 1 Operations,Leakage Past Pressurizer PORVs & Pressurizer Overpressure Protection Sys Values Observed. Cause Not Stated.Porvs Modified
05000311/LER-1983-023, Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired8 June 1983Corrected LER 83-023/03L-0:on 830117-0418,seven Containment Isolation Valves Experienced Leakage Rates Greater than Max Range of Test Equipment.Total Containment Type B & C Leakage Could Not Be Demonstrated.Valves Repaired
05000311/LER-1984-010, Corrected LER 84-010-00:on 840423,during Startup Operations, Turbine Trip & Reactor Trip Occurred.Caused by hi-hi Level in Steam Generator 23.Feedwater Flow Nozzle Replaced & All Sys Performed as Designed23 May 1984Corrected LER 84-010-00:on 840423,during Startup Operations, Turbine Trip & Reactor Trip Occurred.Caused by hi-hi Level in Steam Generator 23.Feedwater Flow Nozzle Replaced & All Sys Performed as Designed
05000311/LER-1990-0269 July 1990LER 90-026-00:on 900609,radiation Monitoring Sys Channel 2R12B Failed Low.Caused by Design/Equipment Concerns.Failed Components Replaced & Pins Connecting Backplane Replaced W/Longer pins.W/900709 Ltr
05000311/LER-1990-02717 July 1990LER 90-027-00:on 900628,determined That ESF Signal Actuation 2R41C Channel Failed Low Due to 2R45 Interlock.Caused by Design/Equipment Concerns.Engineering Investigated Concerns & Uninterruptable Power Sys installed.W/900717 Ltr
05000311/LER-1990-03024 July 1990LER 90-030-00:on 900703,ESF Actuation Containment Purge/ Pressure Vacuum Relief Sys Isolation Occurred After Channel Function Not Placed in Block.Caused by Personnel Error. Individuals Involved Held accountable.W/900724 Ltr
05000354/LER-1988-022, Special Rept 88-006-00:on 880826,HPCI Injection Occurred. Caused by Low Reactor Vessel Level Signal Following Reactor Scram Described in LER 88-022-00.HPCI Injection Nozzle Usage Factor Not Calculated21 November 1988Special Rept 88-006-00:on 880826,HPCI Injection Occurred. Caused by Low Reactor Vessel Level Signal Following Reactor Scram Described in LER 88-022-00.HPCI Injection Nozzle Usage Factor Not Calculated
05000354/LER-1990-0085 July 1990LER 90-008-00:on 900604,reactor Bldg Exhaust Radiation Monitor Trip Setpoint Found Nonconservatively High.Caused by Personnel Error.Technicians Disciplined,Rept Reviewed W/All Personnel & Setpoint Included in procedure.W/900705 Ltr
05000354/LER-1990-0095 July 1990LER 90-009-00:on 900607,HPCI Sys Oil Samples Indicated High Water Content & Traces of Sediment Contamination.Caused by Design Deficiency in HPCI Turbine Lube Oil Reservoir. Reservoir Cleaned,Flushed & Wiped down.W/900705 Ltr
AECM-84-0204, Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored6 April 1984Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored
B12541, Rev 10 to QA Program Topical Rept30 June 1987Rev 10 to QA Program Topical ReptBoric Acid
Probabilistic Risk Assessment
Nondestructive Examination
Condition Adverse to Quality
Fire Protection Program
Backfit
B12822, Annual Rept for 198731 December 1987Annual Rept for 1987Hot Short
Safe Shutdown
Boric Acid
Loop seal
Packing leak
High Radiation Area
Fire Barrier
Stroke time
Safe Shutdown Earthquake
Hydrostatic
Emergency Lighting
Excess Flow Check Valve
Earthquake
Control of Heavy Loads
Turbine Missile
Biofouling
Scaffolding
Unidentified leakage
B13145, & Millstone Station Units 1,2 & 3,Annual Rept for 198831 December 1988& Millstone Station Units 1,2 & 3,Annual Rept for 1988
BECO-85-220, Partially Withheld Security Event Rept:On 851204 Vertical Pipe Chase Not Locked.Lock Removed When Surveys Indicated Radiation Level Below Requirement for Locked High Radiation Level.Pipe Chase Will Be Secured9 December 1985Partially Withheld Security Event Rept:On 851204 Vertical Pipe Chase Not Locked.Lock Removed When Surveys Indicated Radiation Level Below Requirement for Locked High Radiation Level.Pipe Chase Will Be Secured
BECO-86-016, Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended20 February 1986Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended
BECO-86-125, Partially Withheld Security Event Rept:On 860826,bomb Threat Received.Search Initiated.No Suspicious Objects Found29 August 1986Partially Withheld Security Event Rept:On 860826,bomb Threat Received.Search Initiated.No Suspicious Objects Found
BECO-86-171, Partially Withheld Security Event Rept:On 861106,temporary Vital Area Barrier Insp Found Barrier Could Be Breached. Barrier Modified & Compensatory Security Measures Released10 November 1986Partially Withheld Security Event Rept:On 861106,temporary Vital Area Barrier Insp Found Barrier Could Be Breached. Barrier Modified & Compensatory Security Measures Released
BECO-86-173, Partially Withheld Security Event Rept:On 861107,HVAC Duct, Penetrating Vital Area,Removed by Contracted Craft Workers Before Notifying Security.Cause Not Stated.Security Oversight of Subj Contract Work Intensified12 November 1986Partially Withheld Security Event Rept:On 861107,HVAC Duct, Penetrating Vital Area,Removed by Contracted Craft Workers Before Notifying Security.Cause Not Stated.Security Oversight of Subj Contract Work Intensified
FVY-86-105, Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl10 November 1986Part 21 Rept Re Design Defect Relating to Limitorque Motor Operators Mfg Prior to 1975.Mfg Contacted & Retrofit Kits Installed on safety-related & nonsafety-related Operators. Addl Info Encl
IA-84-843, Safety Evaluation Supporting Amend 25 to License DPR-7530 August 1984Safety Evaluation Supporting Amend 25 to License DPR-75Fire Barrier
Nondestructive Examination
Liquid penetrant
IA-84-930, Safety Evaluation Supporting Amends 105 & 99 to Licenses DPR-31 & DPR-41,respectively24 August 1984Safety Evaluation Supporting Amends 105 & 99 to Licenses DPR-31 & DPR-41,respectively
IA-85-826, Partially Released Commission Paper Recommending NRC Response to co-owner Petition for Exemption from License Fee for Withdrawn CP Be in Form of Order.Draft Order Encl25 November 1985Partially Released Commission Paper Recommending NRC Response to co-owner Petition for Exemption from License Fee for Withdrawn CP Be in Form of Order.Draft Order Encl
IA-86-299, Partially Deleted Commission Paper Informing That TMI Alert, Inc Requested Dismissal of Order Granting C Husted Hearing & to Stay Proceedings Pending Resolution of Motion to Dismiss7 March 1986Partially Deleted Commission Paper Informing That TMI Alert, Inc Requested Dismissal of Order Granting C Husted Hearing & to Stay Proceedings Pending Resolution of Motion to Dismiss
IA-86-367, Partially Withheld Affirmative Adjudicatory Issue Re CBS 850324 Broadcast of 60 Minutes on Const of Shoreham5 December 1985Partially Withheld Affirmative Adjudicatory Issue Re CBS 850324 Broadcast of 60 Minutes on Const of Shoreham
IA-87-213, SER Finding Facility Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 3,except for Accumulator Tank Level & Pressure Instrumentation,Containment Sump Water Temp Instrumentation & Quench Tank Temp Instrumentation11 June 1986SER Finding Facility Design Acceptable W/Respect to Conformance to Reg Guide 1.97,Rev 3,except for Accumulator Tank Level & Pressure Instrumentation,Containment Sump Water Temp Instrumentation & Quench Tank Temp InstrumentationBoric Acid
IA-87-439, Partially Withheld Secy Rept Re 861020 Order Issued by IE to Licensee to Show Cause Why Operating License Should Not Be Modified to Prohibit Use of Radios,Tapes & Other Entertainment Devices in Plant Control Rooms28 January 1987Partially Withheld Secy Rept Re 861020 Order Issued by IE to Licensee to Show Cause Why Operating License Should Not Be Modified to Prohibit Use of Radios,Tapes & Other Entertainment Devices in Plant Control Rooms
IR 05000311/197901910 November 1979Updated LER 79-054/01X-1:on 790824,three Snubbers on Main Feedwater 14 During Refueling Outage Per Followup to NRC Insp Rept 50-311/79-19.Caused by Extreme Shock Load.Snubbers Replaced
IR 05000482/198501930 September 1985Allegation Review Data Sheet for Case 4-85-A-050 Re Mishandling of Document Control Program.Concerns Addressed in Insp Rept 50-482/85-19.Dept of Labor & Allegation Cases Closed
IR 05000482/198503128 August 1985Allegation Review Data Sheet for Case 4-85-A-077 Re 6 Rem Exposure in Containment Bldg Due to Pipe Break.Allegation Investigated During Insp 50-482/85-31 on 850715-19 & Found UnsubstantiatedOverexposure
L-83-479, Annual Rept on Changes,Tests & Experiments Made W/O Prior Commission Approval from Jul 1982 - June 198330 June 1983Annual Rept on Changes,Tests & Experiments Made W/O Prior Commission Approval from Jul 1982 - June 1983Safe Shutdown
Boric Acid
Non-Destructive Examination
Hydrostatic
Nondestructive Examination
Temporary Modification
Emergency Lighting
Earthquake
Coast down
L-84-224, Rept of Changes,Tests & Experiments Made W/O Prior Commission Approval,Jul 1983 - June 198430 June 1984Rept of Changes,Tests & Experiments Made W/O Prior Commission Approval,Jul 1983 - June 1984Safe Shutdown
Boric Acid
Emergency Lighting
Locked High Radiation Area
Design basis earthquake
Earthquake
Scaffolding