ML20062N318
From kanterella
| ML20062N318 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/13/1982 |
| From: | Raynor J, Wenderlich R BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20062N311 | List: |
| References | |
| LER-82-021-03L-01, LER-82-21-3L-1, NUDOCS 8208230087 | |
| Download: ML20062N318 (2) | |
Similar Documents at Calvert Cliffs | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000317/LER-1990-0191990-07-20020 July 1990
[Table view]LER 90-019-00:on 900622,determined That Inadequate Breaker Coordination Resulted in Condition Outside Design Basis. Root Cause of Improperly Sized Breaker Not Determined. W/900720 Ltr 05000318/LER-1987-005, Revised LER 87-005-00,correcting Block 15 to Reflect 870501 as Supplemental Rept Expected Submittal Date1987-08-0606 August 1987 Revised LER 87-005-00,correcting Block 15 to Reflect 870501 as Supplemental Rept Expected Submittal Date 05000317/LER-1984-004, Updated LER 84-004-01:on 840228,charging Pumps 12 & 13 Taken Out of Svc Due to Excessive Packing Leakage.Caused by Plunger Packing Failure.Evaluation of Alternative Charging Pump Packing Matls in Progress1984-04-25025 April 1984 Updated LER 84-004-01:on 840228,charging Pumps 12 & 13 Taken Out of Svc Due to Excessive Packing Leakage.Caused by Plunger Packing Failure.Evaluation of Alternative Charging Pump Packing Matls in Progress 05000318/LER-1983-043, Updated LER 83-043/03X-1:on 830809,following Reactor Trip, Steam Generator Safety Valve Failed to Reseat.Caused by Missing Pin.Valves Inspected to Ensure That Blowdown Ring & Pin Not worn.W/840330 Ltr1984-03-30030 March 1984 Updated LER 83-043/03X-1:on 830809,following Reactor Trip, Steam Generator Safety Valve Failed to Reseat.Caused by Missing Pin.Valves Inspected to Ensure That Blowdown Ring & Pin Not worn.W/840330 Ltr 05000318/LER-1983-046, Updated LER 83-046/03X-1:on 830906,penetration Room Exhaust Fan 21 Would Not Start on Containment Isolation Sys Signal While Performing Surveillance Test STP-0-22.Caused by Intermittently Failing Module.Module removed.W/8403301984-03-30030 March 1984 Updated LER 83-046/03X-1:on 830906,penetration Room Exhaust Fan 21 Would Not Start on Containment Isolation Sys Signal While Performing Surveillance Test STP-0-22.Caused by Intermittently Failing Module.Module removed.W/840330 Ltr 05000317/LER-1983-046, Updated LER 83-046/01X-1:on 830816,swing Diesel Generator 12 Shut Down on Loss of Fuel Oil During Surveillance.Caused by Isolation of Day Tank Level Switches,Preventing Fuel Oil Transfer Pump & Low Level Alarm actuation.W/840331984-03-30030 March 1984 Updated LER 83-046/01X-1:on 830816,swing Diesel Generator 12 Shut Down on Loss of Fuel Oil During Surveillance.Caused by Isolation of Day Tank Level Switches,Preventing Fuel Oil Transfer Pump & Low Level Alarm actuation.W/840330 Ltr 05000317/LER-1981-058, Updated LER 81-058/03X-1:on 810721,emergency Diesel Generator 12 to 4 Kv Bus 21 out-of-svc.Caused by Stuck Auxiliary Contact in Emergency Diesel Generator 12 Output Breaker to 4 Kv Bus 14.Switch replaced.W/840330 Ltr1984-03-30030 March 1984 Updated LER 81-058/03X-1:on 810721,emergency Diesel Generator 12 to 4 Kv Bus 21 out-of-svc.Caused by Stuck Auxiliary Contact in Emergency Diesel Generator 12 Output Breaker to 4 Kv Bus 14.Switch replaced.W/840330 Ltr 05000317/LER-1983-034, Updated LER 83-034/03X-1:on 830525,ECCS Pump Room Cooler 12 Taken Out of Svc.Cause Unknown.Supply Piping & Strainers Disassembled,Inspected & Cleaned.New Mechanical Preventive Maint Procedures implemented.W/840306 Ltr1984-03-0606 March 1984 Updated LER 83-034/03X-1:on 830525,ECCS Pump Room Cooler 12 Taken Out of Svc.Cause Unknown.Supply Piping & Strainers Disassembled,Inspected & Cleaned.New Mechanical Preventive Maint Procedures implemented.W/840306 Ltr 05000318/LER-1981-025, Updated LER 81-025/03X-1:on 810430 & 0514,reactor Protective Sys Channel B Trip Units 1,3,7,8 & 10 Bypassed to Investigate Problem w/T-hot Channel B.Caused by Failure of Two Oscillators in Transmitter Circuitry1984-03-0505 March 1984 Updated LER 81-025/03X-1:on 810430 & 0514,reactor Protective Sys Channel B Trip Units 1,3,7,8 & 10 Bypassed to Investigate Problem w/T-hot Channel B.Caused by Failure of Two Oscillators in Transmitter Circuitry 05000317/LER-1981-032, Updated LER 81-032/03X-1:on 810420,reactor Protective Sys Channel D Hi Power Thermal Margin/Low Pressure & Axial Shape Index Trip Units Bypassed for Maint.Caused by Oscillator Noise in transmitter.W/840305 Ltr1984-03-0505 March 1984 Updated LER 81-032/03X-1:on 810420,reactor Protective Sys Channel D Hi Power Thermal Margin/Low Pressure & Axial Shape Index Trip Units Bypassed for Maint.Caused by Oscillator Noise in transmitter.W/840305 Ltr 05000317/LER-1983-037, Updated LER 83-037/03X-1:on 830718,response Time of Trip Circuit Breakers 3 & 4 Undervoltage Trip Devices Slower than Tech Spec Limits.Caused by Setpoint Drift.Setpoints adjusted.W/840305 Ltr1984-03-0505 March 1984 Updated LER 83-037/03X-1:on 830718,response Time of Trip Circuit Breakers 3 & 4 Undervoltage Trip Devices Slower than Tech Spec Limits.Caused by Setpoint Drift.Setpoints adjusted.W/840305 Ltr 05000318/LER-1983-036, Updated LER 83-036/03X-1:on 830719,response Time for Reactor Trip Circuit Breakers 4 & 7 Undervoltage Devices Indicated Slower than Tech Spec Limits.Caused by Setpoint Drift & Worn Front Frame Assembly mechanisms.W/840305 Ltr1984-03-0505 March 1984 Updated LER 83-036/03X-1:on 830719,response Time for Reactor Trip Circuit Breakers 4 & 7 Undervoltage Devices Indicated Slower than Tech Spec Limits.Caused by Setpoint Drift & Worn Front Frame Assembly mechanisms.W/840305 Ltr 05000317/LER-1983-049, Updated LER 83-049/03X-1:on 830818,auxiliary Feedwater Pump 11 Found Inoperable.Caused by Stage & Shaft piece-balance Being Bound Up.Parts replaced.W/840305 Ltr1984-03-0505 March 1984 Updated LER 83-049/03X-1:on 830818,auxiliary Feedwater Pump 11 Found Inoperable.Caused by Stage & Shaft piece-balance Being Bound Up.Parts replaced.W/840305 Ltr 05000318/LER-1981-030, Updated LER 81-030/03X-1:on 810305,discovered Temp Transmitter 122HB Out of Tolerance in Nonconservative Direction.Caused Two Oscillators Producing Noise on Transmitter Output.Transmitter replaced.W/840305 Ltr1984-03-0505 March 1984 Updated LER 81-030/03X-1:on 810305,discovered Temp Transmitter 122HB Out of Tolerance in Nonconservative Direction.Caused Two Oscillators Producing Noise on Transmitter Output.Transmitter replaced.W/840305 Ltr 05000318/LER-1983-074, Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/8402091984-02-0909 February 1984 Updated LER 83-074/03X-1:on 831223,main Steam Supply Valve to Steam Driven Auxiliary Feedwater (AFW) Pumps Failed, Causing AFW Pump 21 to Start.Caused by Insufficient Torque on Casing Cap Screws.New Diaphragm installed.W/840209 Ltr 05000317/LER-1983-047, Updated LER 83-047/03X-1:on 830822,control Room Air Conditioner Compressor 12 Failed to Run W/Start Signal. Caused by Compressor Trip Due to High Pressure.High Pressure Switch reset.W/840126 Ltr1984-01-26026 January 1984 Updated LER 83-047/03X-1:on 830822,control Room Air Conditioner Compressor 12 Failed to Run W/Start Signal. Caused by Compressor Trip Due to High Pressure.High Pressure Switch reset.W/840126 Ltr 05000318/LER-1983-064, Updated LER 83-064/03X-1:on 831105,after Obtaining Results of Unit 1 HPSI Flow Balance Test,Six Unit 2 HPSI Header Isolation Valves Required Adjustment.Caused by Inadequate Procedures.Maint Procedures revised.W/840124 Ltr1984-01-24024 January 1984 Updated LER 83-064/03X-1:on 831105,after Obtaining Results of Unit 1 HPSI Flow Balance Test,Six Unit 2 HPSI Header Isolation Valves Required Adjustment.Caused by Inadequate Procedures.Maint Procedures revised.W/840124 Ltr 05000318/LER-1983-052, Revised LER 83-052/03X-1:on 830928,auxiliary Feedwater Pump 23 Found Inoperable Due to Tripped Protective Relays. Probably Caused by Workers Shorting Internal Breaker Circuits When Working Scaffolding W/Door open.W/831028 Ltr1983-10-28028 October 1983 Revised LER 83-052/03X-1:on 830928,auxiliary Feedwater Pump 23 Found Inoperable Due to Tripped Protective Relays. Probably Caused by Workers Shorting Internal Breaker Circuits When Working Scaffolding W/Door open.W/831028 Ltr 05000318/LER-1983-007, Followup LER 83-007/01T-0:on 830203,de-energization of Reactor Protection Sys (RPS) Channels Caused PORV & Pressurizer Quench Tank Rupture Disk to Open.Caused by Blown Fuse in RPS Channel a Due to Crossed Leads in Inverter 211983-02-18018 February 1983 Followup LER 83-007/01T-0:on 830203,de-energization of Reactor Protection Sys (RPS) Channels Caused PORV & Pressurizer Quench Tank Rupture Disk to Open.Caused by Blown Fuse in RPS Channel a Due to Crossed Leads in Inverter 21 ML20062N3181982-08-13013 August 1982 LER-021/03L-0:on 820714,22B Safety Injection Tank Pressure Found Decreased to 197 Psig on 820427.Caused by Loop Isolator Failure.Isolator Replaced 05000317/LER-1982-022, Updated LER 82-022/01T-1:on 820503,total Type B & C Penetration Leakage Calculations Compared to Wrong Spec. Caused by Incorrectly Revised Local Leak Rate Surveillance Test Procedure.Procedure Revised1982-07-22022 July 1982 Updated LER 82-022/01T-1:on 820503,total Type B & C Penetration Leakage Calculations Compared to Wrong Spec. Caused by Incorrectly Revised Local Leak Rate Surveillance Test Procedure.Procedure Revised ML20062F7081978-12-14014 December 1978 /01x-0 on 781213:reactor Was Made Critical w/11 Component Cooling Heat Exchanger Out of Svc & 11 Saltwater sub-sys Partially Drained.Caused by Personnel Error ML20062G1191978-12-14014 December 1978 /03L-0 on 781117: 5 Halon sub-sys Discharged When Door to 22 Inverter Was Open.Caused by Thermal Detector Being Overly Sensitive to Rate of Rise of Temp.When Door Opened,Internal Airflow Disturbed,Setting Off Detector ML20062E9211978-12-0707 December 1978 /03L-0 on 781113:during Normal Oper the Containment Particulate Radioactivity Monitor Failed Low at 1110.Caused by Disconnection of Signal Cable to Monitor. Cable Connected & Monitor Returned to Svc ML20062E8961978-12-0707 December 1978 /03L-0 on 781115:during Normal Oper Periodic Water Inventory Balance Indicated That Unidentified Reactor Coolant Leakage Was 1.72 Gpm at 0600.Leak Identified as Cracked Weld ML20062D8011978-11-24024 November 1978 /03L-0 on 781115:RWT Level Discovered to Be at 455 Inches.Caused by Rad-Chem Technician'S Failure to Fully Close Local Sample Valve After Drawing Routine Sample. Technician Has Been Reinstructed in Valve Sampling ML20062D7181978-11-24024 November 1978 /03L-0 on 781103:in Routine Surveillance test,11 Auxiliary Feed Pump Was Tripped Per Procedure & Oper Was Unable to Reset Throttle Valve Due to Binding.Assembly Was Freed Upon Lubrication of Stem & Nut ML20062D7691978-11-17017 November 1978 /03L-0 on 781031:solenoid Valve 1-SV-4043 for Main Steam Isolation Valve Hydraulic Accumulators Was Leaking Due to Failure of 1 of 4 O Ring Seals.Cause of Ring Failure Unknown.All 4 Seals Replaced & Valve Returned to Svc ML20062D3411978-11-16016 November 1978 /03L-0 on 781020:pump for Radiat Monitors Seized, Perhaps Due to Graphite Particles from Pump Being Deposited in Bearings.A Normal End of Life Failure.Code Pump Model 6 ML20062D0471978-11-13013 November 1978 /01t-0 on 781025:during LPPT in Mode 2,containment Air Lock Was Opened to Repair Failed Oper Mechanism & Was Kept Ajar,Due to Misunderstanding Between Supervisor & Maintenance Personnel.All Personnel Have Been Reinstructed ML20062D0361978-11-10010 November 1978 /03L-0 on 781025:during Oper,Reactor Protec Instru Wide Range Logarithmic Neutron Flux Monitor Channel a Read 2 Decades Lower than Other Channels,Due to Connector,For Channel a Not Being Dried Completely When Recently Cleaned ML20062C8041978-11-0202 November 1978 /01T-0 on 781023:during Routine Test of Steam Generator Isolation Signal logic,21 Main Steam Isolation Valve Failed to Shut Upon Sgisa & Sgisb Signal or Hand Switch in Control Room,Due to Sticking MSIV Solenoid Valves ML20062C6941978-10-24024 October 1978 /01X-0 on 781023:during Inspec of Steam Generator Isolation Signal logic,21 Main Steam Isolation Valves Failed to Shut When Given Sgisa & Sgisb Signal.Cause Undetermined 1990-07-20 Category:TEXT-SAFETY REPORT MONTHYEARML20217G6971999-09-30030 September 1999
[Table view]Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. 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 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 ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With 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 ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models 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 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 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 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 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 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 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 ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30 |
Text
Retrieved from "https://kanterella.com/w/index.php?title=ML20062N318&oldid=2674801"