Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20045G8611993-07-0909 July 1993 LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr ML20005D6611989-12-0606 December 1989 LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr ML20024E1721983-07-14014 July 1983 Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr ML20028G3801983-01-27027 January 1983 Uptated LER 82-010/03X-1 on 820212,following Reactor Trip, Element Assembly 19 Discovered Stuck at 8-inch Withdrawn Position.Cause Undetermined.Control Element Assembly & Associated Bundle Inspected ML20052J0421982-05-14014 May 1982 LER 82-018/03L-0:on 820417,control Element Assembly 21 Dropped Into Core After Electricians Inadvertently Disconnected Power,Resulting in Pressurizer Level Deviation Exceeding Tech Spec Limit.Caused by Personnel Error ML20003C6001981-03-0101 March 1981 Updated LER 81-002/03L-1:on 810108 & 0227,diesel Generator 12 Started Automatically.Generator Was Stopped & Start Failure Alarm Received.Caused by Insufficient Contact Wipe by Local Break Glass Start Switch.Actuator Fitting Removed ML20003A3881981-01-27027 January 1981 LER 80-066 Has Been Cancelled ML19345B8391980-11-26026 November 1980 LER 80-050/03L-0:on 801027,wide Range ex-core Nuclear Instrument Channel B Failed.Caused by Greater than or Equal to 15-volt Dc Power Supply Having Low Supply W/Ac Ripple. Power Supply Replaced ML19323C4191980-05-13013 May 1980 LER 80-024/03L-0:on 800417,during Containment Entry ,Leak in Middle Seal Instrument Line Flexible Hose Discovered.Cause Unknown.Failed Part Is Inside Containment Bldg & Is Still Radiologically Contaminated ML19208A8031979-09-13013 September 1979 LER 79-034/03L-0:on 790813,during Routine Surveillance Test, Control Element Assembly Deviation Exceeded 7.5 Inches Required to Initiate Assembly Motion Inhibit.Caused by Circuit Failing,W/High Conduction Affecting Other Failures ML19246A5801979-06-25025 June 1979 LER 79-019/03L-0 on 790606:discovered That Number 11 Control Room Air Conditioning Unit Breaker Had Tripped.Caused by Windings of Compressor Motor Exceeding Resistance Acceptance Criteria.Compressor Replaced 1993-07-09
[Table view] Category:RO)
MONTHYEARML20045G8611993-07-0909 July 1993 LER 93-003-00:on 930610,dual Unit Trip Occurred Due to Partial Loss of Offsite Power.Flashover Protection Relay for Breaker 552-61 Replaced & Training for Personnel W/ Access to Relays Will Be reinforced.W/930709 Ltr ML20005D6611989-12-0606 December 1989 LER 89-018-00:on 891106,discovered That Many Air Operated Control Valves & piston-operated Dampers Which Utilize safety-related Air Accumulators Would Not Have Performed as Expected After Loss of air.W/891206 Ltr ML20024E1721983-07-14014 July 1983 Updated LER 81-015/03X-1:on 810226,sample Pump for Control Room Radiation Monitor Found Out of Svc,Rendering Automatic Recirculation of Control Room Ventilation Sys on High Radiation Inoperable.Caused by seizure.W/830714 Ltr ML20028G3801983-01-27027 January 1983 Uptated LER 82-010/03X-1 on 820212,following Reactor Trip, Element Assembly 19 Discovered Stuck at 8-inch Withdrawn Position.Cause Undetermined.Control Element Assembly & Associated Bundle Inspected ML20052J0421982-05-14014 May 1982 LER 82-018/03L-0:on 820417,control Element Assembly 21 Dropped Into Core After Electricians Inadvertently Disconnected Power,Resulting in Pressurizer Level Deviation Exceeding Tech Spec Limit.Caused by Personnel Error ML20003C6001981-03-0101 March 1981 Updated LER 81-002/03L-1:on 810108 & 0227,diesel Generator 12 Started Automatically.Generator Was Stopped & Start Failure Alarm Received.Caused by Insufficient Contact Wipe by Local Break Glass Start Switch.Actuator Fitting Removed ML20003A3881981-01-27027 January 1981 LER 80-066 Has Been Cancelled ML19345B8391980-11-26026 November 1980 LER 80-050/03L-0:on 801027,wide Range ex-core Nuclear Instrument Channel B Failed.Caused by Greater than or Equal to 15-volt Dc Power Supply Having Low Supply W/Ac Ripple. Power Supply Replaced ML19323C4191980-05-13013 May 1980 LER 80-024/03L-0:on 800417,during Containment Entry ,Leak in Middle Seal Instrument Line Flexible Hose Discovered.Cause Unknown.Failed Part Is Inside Containment Bldg & Is Still Radiologically Contaminated ML19208A8031979-09-13013 September 1979 LER 79-034/03L-0:on 790813,during Routine Surveillance Test, Control Element Assembly Deviation Exceeded 7.5 Inches Required to Initiate Assembly Motion Inhibit.Caused by Circuit Failing,W/High Conduction Affecting Other Failures ML19246A5801979-06-25025 June 1979 LER 79-019/03L-0 on 790606:discovered That Number 11 Control Room Air Conditioning Unit Breaker Had Tripped.Caused by Windings of Compressor Motor Exceeding Resistance Acceptance Criteria.Compressor Replaced 1993-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000317/LER-1999-006, :on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With1999-10-22022 October 1999
- on 990922,manual Reactor Trip Was Noted.Caused by Inadequate Electrical Current Determination.Evaluated Trip Risk Assessment Process for Enhancements.With
ML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With 05000317/LER-1998-011, :on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With1999-09-20020 September 1999
- on 980428,prematurely Released Fire Watch Was Noted.Caused by Inadequate Cure Time Communications.Revised Configuration Control Documents.With
ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20211J3531999-09-0101 September 1999 Safety Evaluation Supporting Amends 231 & 207 to Licenses DPR-53 & DPR-69,respectively ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-005, :on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With1999-08-23023 August 1999
- on 990720,corrosion Behavior & Onset of Oxide Spalling of High Duty Fuel Noted on Fuel Assemblies.Caused by Normal Phenomenon.Operability Evaluation for Current Cycle Operation Will Be Performed.With
05000317/LER-1999-004, :on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With1999-08-23023 August 1999
- on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With
ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-003, :on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With1999-07-30030 July 1999
- on 990701,recognized That Unapproved Methodology Was Used to Allow CREVS to Remain Operable in accept-as-is Condition.Regulatory Notification Required in 10CFR50.72(b)(1)(ii)(A) Performed.With
ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-039, Part 21 Rept Re Defect of ABB 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of ABB 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified LD-99-035, Part 21 Rept Re ABB 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re ABB 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with 05000317/LER-1999-002, :on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With1999-05-25025 May 1999
- on 990401,discovered That Radioactive Sources Were Lost.Caused by Inadequate Control.Searched Storage Locations on Three Separate Occasions,Including Document Storage Locations.With
ML20206U7031999-05-18018 May 1999 Rev 1 to Ran 97-031, Main CR Fire Analysis for IPEEE Section 4-1 ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on ABB CE ECCS Performance Evaluation Models ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20205J8331999-04-0707 April 1999 Safety Evaluation Concluding That Security Lighting,Portable Lighting & Helmet Lights,As Described by Licensee Satisfies Underlying Purpose of 10CFR50,App R,Section Iii.J.Grants Licensee Request for Exemption ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20204B5961999-03-17017 March 1999 Corrected Page 7 to SER for Amend 205 for License DPR-69. Staff Deleted Word Not on Line One of Page 7 ML20207L2991999-03-0808 March 1999 Safety Evaluation Supporting Amend 205 to License DPR-69 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons 05000317/LER-1997-010, :on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With1999-01-29029 January 1999
- on 971210,1B EDG Failed to Start During Performance of Routine Surveillance Test.Caused by Piece of Stainless Steel Foreign Matl in Governor Hydraulic Boundaries.Stainless Steel Replaced.With
ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed 05000317/LER-1998-009, :on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With1999-01-0808 January 1999
- on 980408,required Hourly Fire Watch Missed, When Contractor Maint Worker Failed to Perform Fire Watch Patrol.Caused by Personnel Error.Plant Mgt Reiterated Expectation to Contractor Personnel.With
ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20196J6771998-12-0808 December 1998 Safety Evaluation Supporting Amends 229 & 204 to FOLs DPR-53 & DPR-69,respectively ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative 05000317/LER-1998-008, :on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With1998-11-11011 November 1998
- on 981020,reactor Protective Sys Instrumentation TS Error Was Noted.Caused by Incorrect Use of Thermal Power in Ts.Revised TSs 3.3.1 & 3.3.2.With
ML20195D4271998-11-0505 November 1998 Safety Evaluation Supporting Amend 203 to License DPR-69 ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With 1999-09-30
[Table view] |