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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045H4171993-07-0909 July 1993 Special Rept:On 930608,fire Detection for Containment 11A & 11B Reactor Coolant Pump Motor Bay Disabled to Prevent Spurious Trouble Alarms & Not Restored within 14 Days. Caused by High Temps in Bays.Temp Monitored Once Per Hour ML20044C1671993-03-11011 March 1993 Special Rept:On 930211,wide Range Noble Gas Monitor (Wrngm) Removed from Svc When Automatic 8-h Check Source Failed Due to Failure of Preamplified Board.Board Replaced on 930217 & Wrngm Restored to Operable Status on 930222 ML20043F7911990-06-13013 June 1990 Special Rept:On 900507,diesel Fire Pump Inoperable in Excess of 7 Days.Caused by Inability to Perform Capacity Test on Pump & Return Pump to Svc Due to Performance of Engineering Evaluation on Relief Valve to Flanged Pipe Connection ML20043H0461990-06-11011 June 1990 Ro:On 900503,heat Detection Sys Protecting East Reactor Coolant Pump Bay Disabled for More than 14 Days.Sys Disabled So That Detectors Could Be Removed to Facilitate Access to Reactor Coolant Pump During Maint Outage ML20043B1051990-05-15015 May 1990 Special Rept:On 900330,meteorological Info Data Acquisition Sys Found Out of Svc.No Cause of Malfunction Identified. Channel Declared Operable on 900418 ML20012C5151990-03-13013 March 1990 Special Rept:On 900209,four Missing Fire Dampers in Battery Room Supply & Exhaust Ducts Noted.Hourly Fire Watch Patrol Established.Facility Change Request 90-019 Initiated to Install Fire Dampers ML20012A3321990-02-28028 February 1990 Special Rept:Unavailability of Primary Method for post- Accident Sampling of Iodines & Particulates in Main Vent Stack Effluent.Caused by Sample Line Heat Trace & Thermal Insulation Deficiencies.Design Inadequacies Being Corrected ML20006A1951990-01-19019 January 1990 Special Rept:On 891219,fire Door 427 Located in Stairwell AB-2 in Auxiliary Bldg Inoperable for More than 7 Days. Caused by Door Latch Not Working.Fire Watch Patrol Established & Door Repair Completed on 891228 ML20006A3331990-01-19019 January 1990 Special Rept:On 900110,discovered That Containment Isolation Valve for Containment Hose Station Riser Would Not Open Upon Remote Initiation from Control Room.Caused by Dirt Contact within Motor Operator.Valves Will Be Checked ML20005G2651990-01-11011 January 1990 Special Rept:On 900110,containment Isolation Valve for Containment Hose Station Riser Failed to Open Upon Remote Initiation from Control Room.Containment Isolation Valve Manually Opened.Detailed Special Rept Will Be Provided ML20005E2891989-12-27027 December 1989 Special Rept:On 891128,evidence of Sediment in Fuel Oil Storage Tanks 21 & 11 Found,Declaring Tanks & Diesel Fire Pump Inoperable.Tanks Were Drained,Cleaned & Refilled ML20005D9131989-12-21021 December 1989 Special Rept:On 891211,fire Protection Valves 653 & 413 Not Included in Surveillance Test STP-M-693-0 & Found in Open Position.Both Valves Cycled within 24 H of Telephone Notification & Procedure Revised to Include Both Valves ML19332G1591989-12-12012 December 1989 Special Rept:On 891211,failure to Include Fire Protection Valves 653 & 413 in Surveillance STP M-0693-0 Discovered. Valves Tested & Found Operable by Performing Complete Cycle Test.No Effect on Plant Operation Exists ML19354D4821989-10-30030 October 1989 Special Rept:On 890720,Halon Sys for Unit 1 Switchgear Room Inoperable.Caused by Personnel Error.Hourly Firewatch Established.Solenoid Functionally Tested Satisfactorily, Declared Operable & Connected to Halon Bank ML19324B3561989-10-20020 October 1989 Updates 890803 & 0905 Special Repts Re Missing Fire Damper & Inoperable Fire Damper.Due to Delays in Obtaining Necessary Components,Completion Date for Work on Dampers & Barrier Now Anticipated for 891231 Instead of 891031 ML20028E0581983-01-13013 January 1983 RO 83-03:on 830112,air Line Supplying Instrument Air Became Disconnected,Causing Auxiliary Feedwater Regulating Valves to Fail Open,Rendering FSAR Steam Line Break Analysis Invalid.Instrument Air Line Repaired ML20052F8531982-05-0404 May 1982 RO 82-22/1T:confirms That from 801218 Until 820418,all Unit Operations in Excess of 200 F Have Been Performed W/Combined Leakage Rate Greater than Specs for Penetrations & Valves Subj to Type B & C Testing ML19350F0971981-06-16016 June 1981 Ro:On 810613,C-E Advised That Pipe Fittings Immediately Upstream of RCS Code Safety Valves Do Not Have Proper Inside Diameter.Reduction in Inlet Pipe Diameter Does Not Constitute Safety Hazard.Followup Rept Forthcoming ML19350F0931981-06-15015 June 1981 Ro:On 810612,NRC Resident Inspector Discovered 1-LS-4142-C (Refueling Water Tank Low to Reactor Analysis & Safety) Isolated.Personnel Verified Level Switch Operable by Performing Surveillance Test.Followup Rept to Be Submitted ML20003A9831981-02-0404 February 1981 RO 81-08:on 810203,fire Hose Stations in Unit 2 Containment Bldg & Auxiliary Bldg Found Isolated W/O Required Routing of Backup Fire Hoses.Cause Not Stated.Backup Fire Hoses Rigged & Fire Watches Stationed ML20049A4081981-01-20020 January 1981 RO 81-005 on 810118:power Operated Relief Valve RC-404-ERV Inadvertently Opened.Caused by Pressure Indicating Controller PIC-103-1 Failing High.Power Relief Isolation RC-405-MOV Shut,Terminating Discharge ML20049A3771980-12-16016 December 1980 RO 80-65 (U-1):on 801215,during Mode 5 Operations,Shutdown Cooling Flow Stopped to Perform Leak Rate Test on Penetration 41 W/O Verifying That Charging Pumps Were de-energized or That Flow Paths Were Closed ML19340C2991980-11-0707 November 1980 RO 80-49:on 801106,bus 21 4 Kv Not Realigned to 500 Kv Black Bus After Maint,Resulting in Continued Supply from 500 Kv Red Bus.Caused by Personnel Oversight.Generators 12 & 21 & 500 Kv Red Bus Verified ML19338G5971980-10-23023 October 1980 RO 80-58, on 801021 W/Control Room Air Conditioning Unit 11 Out of Svc for Maint,Unit 12 Sys Tripped.Sys Restarted by Reset Button.Filter Trains Remained Operable During Event. Complete Rept W/Corrective Actions Will Be Forwarded ML19338E2501980-09-12012 September 1980 RO 80-51:on 800911,during post-maint Test,Control Room Air Conditioning Unit 11 Failed to Start.Attempt to Restart Unit 12 Failed.Cause Not Stated.After Corrective Maint & Repairs Units 11 & 12 Returned to Svc ML19338C6341980-08-13013 August 1980 RO 80-41:on 800812,w/facility Operating at 100% Power,Level in Svc Water Head Tanks 11 & 12 Went from Normal to Full. Caused by Failure of Instrument After Compressor Air Cooler 11.Air Cooler Was Isolated & Sys Restored ML19330B7651980-07-31031 July 1980 ROs 80-37 & 80-35 Confirming Verbal Notification:On 800731, Instrument Tubing Connecting Air Start Sys Headers to Pressure Switches Monitoring Air Receiver Pressure Were Not Seismically Qualified.Mods Underway ML19330B5391980-07-30030 July 1980 Ro:On 800624,oyster Samples Analyzed for gamma-emitting Radionuclides Showed Presence of Ag-110m.Doses Are of No Consequence to Health & Safety of Public ML19330C3111980-07-27027 July 1980 Ro:On 800727,at 100% Power,Facilities Exceeded Rated Thermal Power.Caused by Leak in Steam Generator Blowdown Recovery Heat Exchanger Resulting in Erroneous Input to Core Calorimetric Calculation.Investigation Ongoing ML19330B1051980-07-24024 July 1980 RO 80-32 on 800723,charging Pumps 22,23 & 24 Were Placed Out of Svc for Mechanical Reasons,Leaving Charging Pump 21 W/O Emergency Power.Caused by Operator Failure to Verify safety-related Sys Out of Svc.Corrective Action Forthcoming ML19327A1621980-07-17017 July 1980 RO 80-34:on 800716,w/both Units at 100% Power,Control Room Air Conditioning Units 11 & 12 Tripped.Caused by Collection of Liquid Refrigerant in Respective Condenser Sections ML19262E4321980-05-21021 May 1980 Ro:On 800520,following Manually Initiated Trip,Suction Side Valve Lineup Found to Be Incorrect.Valves Immediately Realigned.Checklist Verifying Valve Alignment Will Be Instituted ML19323G7431980-04-16016 April 1980 Ro:On 800416,NRC Div of Project Mgt Advised Util of Possible Generic Deficiency in FSAR Section 4.3.Boron Dilution Incident Analysis Does Not Analyze When RCS May Be Drained to Middle of Hot Leg w/1% Shutdown Margin ML19260C2121979-11-12012 November 1979 Cycle 4,Preliminary Rept of Power Distribution Episode. ML19254E1941979-10-22022 October 1979 Submits Nonroutine Radiological Environ Operating Rept: on 790827,oyster Samples Analyzed for gamma-emitting Radionuclides Showed Presence of Ag-110m.Review of Data Indicates That Ag-100m in Oysters Is plant-related 1993-07-09
[Table view] Category:LER)
MONTHYEARML20045H4171993-07-0909 July 1993 Special Rept:On 930608,fire Detection for Containment 11A & 11B Reactor Coolant Pump Motor Bay Disabled to Prevent Spurious Trouble Alarms & Not Restored within 14 Days. Caused by High Temps in Bays.Temp Monitored Once Per Hour ML20044C1671993-03-11011 March 1993 Special Rept:On 930211,wide Range Noble Gas Monitor (Wrngm) Removed from Svc When Automatic 8-h Check Source Failed Due to Failure of Preamplified Board.Board Replaced on 930217 & Wrngm Restored to Operable Status on 930222 ML20043F7911990-06-13013 June 1990 Special Rept:On 900507,diesel Fire Pump Inoperable in Excess of 7 Days.Caused by Inability to Perform Capacity Test on Pump & Return Pump to Svc Due to Performance of Engineering Evaluation on Relief Valve to Flanged Pipe Connection ML20043H0461990-06-11011 June 1990 Ro:On 900503,heat Detection Sys Protecting East Reactor Coolant Pump Bay Disabled for More than 14 Days.Sys Disabled So That Detectors Could Be Removed to Facilitate Access to Reactor Coolant Pump During Maint Outage ML20043B1051990-05-15015 May 1990 Special Rept:On 900330,meteorological Info Data Acquisition Sys Found Out of Svc.No Cause of Malfunction Identified. Channel Declared Operable on 900418 ML20012C5151990-03-13013 March 1990 Special Rept:On 900209,four Missing Fire Dampers in Battery Room Supply & Exhaust Ducts Noted.Hourly Fire Watch Patrol Established.Facility Change Request 90-019 Initiated to Install Fire Dampers ML20012A3321990-02-28028 February 1990 Special Rept:Unavailability of Primary Method for post- Accident Sampling of Iodines & Particulates in Main Vent Stack Effluent.Caused by Sample Line Heat Trace & Thermal Insulation Deficiencies.Design Inadequacies Being Corrected ML20006A1951990-01-19019 January 1990 Special Rept:On 891219,fire Door 427 Located in Stairwell AB-2 in Auxiliary Bldg Inoperable for More than 7 Days. Caused by Door Latch Not Working.Fire Watch Patrol Established & Door Repair Completed on 891228 ML20006A3331990-01-19019 January 1990 Special Rept:On 900110,discovered That Containment Isolation Valve for Containment Hose Station Riser Would Not Open Upon Remote Initiation from Control Room.Caused by Dirt Contact within Motor Operator.Valves Will Be Checked ML20005G2651990-01-11011 January 1990 Special Rept:On 900110,containment Isolation Valve for Containment Hose Station Riser Failed to Open Upon Remote Initiation from Control Room.Containment Isolation Valve Manually Opened.Detailed Special Rept Will Be Provided ML20005E2891989-12-27027 December 1989 Special Rept:On 891128,evidence of Sediment in Fuel Oil Storage Tanks 21 & 11 Found,Declaring Tanks & Diesel Fire Pump Inoperable.Tanks Were Drained,Cleaned & Refilled ML20005D9131989-12-21021 December 1989 Special Rept:On 891211,fire Protection Valves 653 & 413 Not Included in Surveillance Test STP-M-693-0 & Found in Open Position.Both Valves Cycled within 24 H of Telephone Notification & Procedure Revised to Include Both Valves ML19332G1591989-12-12012 December 1989 Special Rept:On 891211,failure to Include Fire Protection Valves 653 & 413 in Surveillance STP M-0693-0 Discovered. Valves Tested & Found Operable by Performing Complete Cycle Test.No Effect on Plant Operation Exists ML19354D4821989-10-30030 October 1989 Special Rept:On 890720,Halon Sys for Unit 1 Switchgear Room Inoperable.Caused by Personnel Error.Hourly Firewatch Established.Solenoid Functionally Tested Satisfactorily, Declared Operable & Connected to Halon Bank ML19324B3561989-10-20020 October 1989 Updates 890803 & 0905 Special Repts Re Missing Fire Damper & Inoperable Fire Damper.Due to Delays in Obtaining Necessary Components,Completion Date for Work on Dampers & Barrier Now Anticipated for 891231 Instead of 891031 ML20028E0581983-01-13013 January 1983 RO 83-03:on 830112,air Line Supplying Instrument Air Became Disconnected,Causing Auxiliary Feedwater Regulating Valves to Fail Open,Rendering FSAR Steam Line Break Analysis Invalid.Instrument Air Line Repaired ML20052F8531982-05-0404 May 1982 RO 82-22/1T:confirms That from 801218 Until 820418,all Unit Operations in Excess of 200 F Have Been Performed W/Combined Leakage Rate Greater than Specs for Penetrations & Valves Subj to Type B & C Testing ML19350F0971981-06-16016 June 1981 Ro:On 810613,C-E Advised That Pipe Fittings Immediately Upstream of RCS Code Safety Valves Do Not Have Proper Inside Diameter.Reduction in Inlet Pipe Diameter Does Not Constitute Safety Hazard.Followup Rept Forthcoming ML19350F0931981-06-15015 June 1981 Ro:On 810612,NRC Resident Inspector Discovered 1-LS-4142-C (Refueling Water Tank Low to Reactor Analysis & Safety) Isolated.Personnel Verified Level Switch Operable by Performing Surveillance Test.Followup Rept to Be Submitted ML20003A9831981-02-0404 February 1981 RO 81-08:on 810203,fire Hose Stations in Unit 2 Containment Bldg & Auxiliary Bldg Found Isolated W/O Required Routing of Backup Fire Hoses.Cause Not Stated.Backup Fire Hoses Rigged & Fire Watches Stationed ML20049A4081981-01-20020 January 1981 RO 81-005 on 810118:power Operated Relief Valve RC-404-ERV Inadvertently Opened.Caused by Pressure Indicating Controller PIC-103-1 Failing High.Power Relief Isolation RC-405-MOV Shut,Terminating Discharge ML20049A3771980-12-16016 December 1980 RO 80-65 (U-1):on 801215,during Mode 5 Operations,Shutdown Cooling Flow Stopped to Perform Leak Rate Test on Penetration 41 W/O Verifying That Charging Pumps Were de-energized or That Flow Paths Were Closed ML19340C2991980-11-0707 November 1980 RO 80-49:on 801106,bus 21 4 Kv Not Realigned to 500 Kv Black Bus After Maint,Resulting in Continued Supply from 500 Kv Red Bus.Caused by Personnel Oversight.Generators 12 & 21 & 500 Kv Red Bus Verified ML19338G5971980-10-23023 October 1980 RO 80-58, on 801021 W/Control Room Air Conditioning Unit 11 Out of Svc for Maint,Unit 12 Sys Tripped.Sys Restarted by Reset Button.Filter Trains Remained Operable During Event. Complete Rept W/Corrective Actions Will Be Forwarded ML19338E2501980-09-12012 September 1980 RO 80-51:on 800911,during post-maint Test,Control Room Air Conditioning Unit 11 Failed to Start.Attempt to Restart Unit 12 Failed.Cause Not Stated.After Corrective Maint & Repairs Units 11 & 12 Returned to Svc ML19338C6341980-08-13013 August 1980 RO 80-41:on 800812,w/facility Operating at 100% Power,Level in Svc Water Head Tanks 11 & 12 Went from Normal to Full. Caused by Failure of Instrument After Compressor Air Cooler 11.Air Cooler Was Isolated & Sys Restored ML19330B7651980-07-31031 July 1980 ROs 80-37 & 80-35 Confirming Verbal Notification:On 800731, Instrument Tubing Connecting Air Start Sys Headers to Pressure Switches Monitoring Air Receiver Pressure Were Not Seismically Qualified.Mods Underway ML19330B5391980-07-30030 July 1980 Ro:On 800624,oyster Samples Analyzed for gamma-emitting Radionuclides Showed Presence of Ag-110m.Doses Are of No Consequence to Health & Safety of Public ML19330C3111980-07-27027 July 1980 Ro:On 800727,at 100% Power,Facilities Exceeded Rated Thermal Power.Caused by Leak in Steam Generator Blowdown Recovery Heat Exchanger Resulting in Erroneous Input to Core Calorimetric Calculation.Investigation Ongoing ML19330B1051980-07-24024 July 1980 RO 80-32 on 800723,charging Pumps 22,23 & 24 Were Placed Out of Svc for Mechanical Reasons,Leaving Charging Pump 21 W/O Emergency Power.Caused by Operator Failure to Verify safety-related Sys Out of Svc.Corrective Action Forthcoming ML19327A1621980-07-17017 July 1980 RO 80-34:on 800716,w/both Units at 100% Power,Control Room Air Conditioning Units 11 & 12 Tripped.Caused by Collection of Liquid Refrigerant in Respective Condenser Sections ML19262E4321980-05-21021 May 1980 Ro:On 800520,following Manually Initiated Trip,Suction Side Valve Lineup Found to Be Incorrect.Valves Immediately Realigned.Checklist Verifying Valve Alignment Will Be Instituted ML19323G7431980-04-16016 April 1980 Ro:On 800416,NRC Div of Project Mgt Advised Util of Possible Generic Deficiency in FSAR Section 4.3.Boron Dilution Incident Analysis Does Not Analyze When RCS May Be Drained to Middle of Hot Leg w/1% Shutdown Margin ML19260C2121979-11-12012 November 1979 Cycle 4,Preliminary Rept of Power Distribution Episode. ML19254E1941979-10-22022 October 1979 Submits Nonroutine Radiological Environ Operating Rept: on 790827,oyster Samples Analyzed for gamma-emitting Radionuclides Showed Presence of Ag-110m.Review of Data Indicates That Ag-100m in Oysters Is plant-related 1993-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 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
[Table view] |
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'OAS AND V n ,< ELECTRIC jj CHARLES CENTER . P.O. BOX 1475 BALTIMORE. MARYLAND 21203 ,
[,, s ' , t. EON B. RUSSELL
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- ,, . 3, CAtytRT CLIFFS NUCLEAR POWER PLANT DEPARTMENT x.
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' October 30,1989
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U. S. Nuclear Regulatory Cornmission Washington, DC 20555 m
' ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs ' Nuclear Power Plant i Unit Nos. I _ & 2; Docket Nos. 50-317 & 50-318 '
. Halon Systems Special Report '
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q- Technical Snecification 3.7.11.3a "
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' Gentlemen:-
, . Per . ' the requirements of Technical Specification 3.7.ll.3a, we hereby submit the. l following Special Report . .concerning an inoperable Halon ' system ' for the ~ Unit' I Switchgear Rooms.
Should you have any further questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, eD t
LBR/GLB/bjd (
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4 HALON SYSTEM SPECI AL REPORT BACKGROUND At approximately 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on July 20. 1989, with Unit I shutdown (MODE 5 Cold 1 Shutdown), a Fire and Safety Technician (FAST) discovered that a master solenoid to the Unit i Switchgear Room Halon System was disconnected. This solenoid actuotes the discharge of Halon from three of nine Halon cylinders located on the west wall of the 45-foot elevation Switchgear room. This disconnected solenoid was discovered during the routine performance of Surveillance Test Procedure (STP) M-291-0, "Halon System Valve Position Verification." However, the Halon System Master Solenoids are not checked as part of this STP and, therefore, the performance of the STP did not directly contribute to the discovery of this event.
Upon discovery of the disconnected solenoid, the Shift Supervisor was informed and the Halon System was immediately declared inoperable. The ACTION STATEMENT for Technical Specification 3.7.11.3, "Halon Systems," was entered and an hourly fire watch was established. The solenoid was inspected for damage and returned to its normal position, however, the ACTION STATEMENT remained in effect until an OPERABILITY determination could be made.
Even though there was no indication of damage to the solenoid or associated equipment, a functional test was performed to verify OPERABILITY. A maintenance order was initiated and OPERABILITY of the solenoid was verified by performing Section VII of STP-M-699-1, " Functional Test of 27' and 45' Switchgear Rooms Automatic Halon Release Solenoll Circuit." Upon satisfactory completion of the test, the Halon System was decle.rtd OPERABLE and the ACTION STATEMENT was exited at approximately 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on July 20, 1989.
Further investigation into the event showed that the solenoid was last documented to be out-of-service ' between approximately 0830 and 0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br /> on June 29, 1989. A FAST had performed a fire system impairment tagout at this time in accordance with Calvert Cliffs Instruction CCI-133, "Calvert Cliffs Fire Protection Plan". The Halon System for the 27-foot and 45-foot Switchgear rooms was disabled by disconnecting each of the '
three master solenoids from its associated Halon cylinder bank. This is the standard !
- l. procedure for disabling a Halon system when work being performed in a room might cause j an inadvertent actuation of the Halon System. In this instance, maintenance I technicians wanted to heat a motor-generator coupling on the 27-foot level Switchgear room.
l~ The FAST who performed the tagout on June 29, 1989 believes that tit was unlikely that l
he left one master solenoid diconnected. However, CCI-133 did not require independent i
verification of the fire system impairment tagout. Therefore, there was no independent l
verification by any other personnel that all three master solenoids were actually reconnected on June 29. During the investigation, it was also reported that the master solenoids were observed to be in place on July 14, 1989. This observation occurred during an informal walkdown of the Halon System which was being conducted for the purposes of procedure development. However, this observation was not documented. No l maintenance or other activities were identified during the period between June 29 and l July 20 which would require the Halon System to be disabled in the 27-foot or 45-foot levels of the Switchgear Room. Consequently, since it cannot be determined beyond a reasonable doubt that the master solenoid was reconnected on June 29, we conclude from lL _ _ - . - . _. .
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HALON SYSTEM SPECIAL REPORT the documented evidence that 'the solenoid was inadvertently left disconnected.
This tevent was reported in a four hour report under 10 CFR 50.72(b)(2Xi) and in Licensee Event Report (LER) 89-12-Ol* under 10 CFR 50.73(aX2XiXD) as a condition prohibited by the plant's Technical Specifications.
CAUSE OF INOPERABILITY The root cause of this event was determined to be personnel error resulting from the lack of an approved, written procedure for rendering the Ilalon System inoperable by disabling the three master solenoids. Activities which modify fire protection systems i described in the Technical Specifications are required to be prescribed and accomplished in accordance with documented instructions, procedures, and drawings.
This task was incorrectly considered to be within the skills normally possessed by qualified personnel of the craft and, therefore, the FAST was unaware that a procedure was required. Contributing causes to this event are as follows.
CCI-133, "Calvert Cliffs Fire Protection Plan" does not adequately address the method for taking fire detection or suppression systems out-of-service. CCI-133 does not reference CCI-I l 7, " Temporary Modification Control." The purpose of CCI-ll7 is to ensure that the disabling, bypassing, or changing af systems, sub-systems, or components by some form of temporary modification will be properly reviewed for safety consequences, documented, and controlled. The task of disconnecting the solenoids was not recognized as a temporary modification to the plant. The use of CCI-il7 would have required an independent verification to ensure that all of the master solenoids had been returned to service before declaring the Halon System OPERABLE.,
in addition, CCI-133 does not adequately address when Safety Tagging is required or I its relationship to Fire System impairment Tagging. CCI-Il2, " Safety Tagging" is not I referenced by CCI- 133. The purpose of CCI-il2 is to establish procedures for the tagging of equipment to ensure the safety of personnel and to ensure no adverse effect on operating equipment. Fire System Impairment Tags are placed on fire detection and
- suppression equipment whenever they are taken out-of-service for maintenance. Due to ,
l the ambiguity of these instructions, a Safety Tag was considered not to be required for '
l this task.
l l EFFECT ON UNIT OPERATION l An evaluation of Halon concentration with the three-bottle bank unavailable was l performed. An initial concentration of approximately 6% - was calculated as available for the 45-foot elevation Switchgear room and approximately 3.45% was calculated for the 27-foot Switchgear room. It can be concluded that the Halon system, even with the three-bottle bank inoperable, would have prevented fire spreading within the room as NOTE: Revision 1 of LER 89-12 issued October 27, 1989, revised the event date from July 20, 1989 to June 29, 1989. As a result, the Halon System was declared inoperable for greater than 14 days, (i.e., June 29 - July 20, 1989) and the special report has subsequently been submitted late.
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is-L HALON SYSTEM SPECIAL REPORT '
P well as outside the room. Our bases for this conclusion are provided below:
In the 45-foot Switchgear room the initial discharge concentration of 6% is ,
above the recommended extinguishing concentration of 5% for this type of room.
In the 27-foot Switchgear room the initial discharge concentration of 3.45%, while below the recommended extinguishing concentration, would have ,
stopped flaming combustion and thereby prevented a fire from spreading.
- l The detection systems which actuate the Halon systems were functional.
These systems provide an alarm indication to the Control room. In addition, these systems utilize smoke detectors which respond much faster to fire conditions than heat detectors. Therefore any fire leading to discharge of the Halon system would have still been in an l' incipient stage.
i The plant fire brigade would respond to a fire in time to provide extinguishment . of glowing combustion still remaining after the llalon discharge.
Therefore, there is reasonable assurance that the safety of the plant and the public was not significantly compromised by the event.
1)(MEDIATE CORRECTIVE ACTIONS TAKEN
- The following corrective actions were taken on July 20, 1989
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L . Upon discovery of the event, the I-lalon system was declared INOPERABLE and an hourly. fire watch was established in accordance with Technical li Specification 3.7.11.3. .
. After inspecting the solenoid for any noticeable damage, the solenoid was L connected back to its Halon bank. Therefore, though remaining inoperable
- l. by Technical Specifications, the Halon system was functional.
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. The solenoid was functionally tested satisfactorily and declared OPERABLE, CORRECTIVE ACTIONS TAKEN TO PRECLUDE REOCCURRENCE The following corrective actions have been taken as a result of this event:
p . CCI-133 has been revised to discontinue the use of fire system impairment L
tags and, instead, will reference CCI-i l2 Safety Tagging requirements.
CCI-133 will also require the use of CCI-il7 for temporary modifications to fire : detection and suppression sy:;tems.
. STP-M-291-0 has been revised to require verification that llalon actuator l
solenoids are properly installed. This STP and STP-M-699-1 have also been revised to have distinct verification and sign-offs for each Halon System station.
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i i 15ALON SYSTEM SPECIAL REPORT
. Identification tags have been installed on llalon master solenoids.
. . Warning signs have been placed near llalon. cylinder banks which state, TIRE SUPPRESSION SYSTEM DO NOT DISTURB WITilOUT PERMISSION, CALL FIRE PROTECTION UNIT: X-4755/4931."
1 The following corrective actions will be taken as a result of this event:
. A Quality Assurance Surveillance will be conducted to: (1) evaluate if CCI-ll2 and 117 are applicable to any other plant activities not currently being applied to these CCis and (2) determine if plant personnel (sample selected from cognizant disciplines) have an adequate working knowledge of 3
CCis i12, i17, and 133.
. Fire and Safety personnel will receive training on the revised requirements. j of CCI-133 and CCI-il7. !
. A written procedure will be established for disabling and restoring the Halon System master solenoids.
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