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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML18106A9621998-11-16016 November 1998 Special Rept:On 981006,train B of Reactor Vessel Level Indicating Sys Was Indicating Malfunction.Caused by Loss of Fill in Capillary Sensing Line.Extensive Troubleshooting Was Performed on Sys ML18106A8591998-08-31031 August 1998 Special Rept:On 980816,RMS Channel 1R15 Inoperable for Greater than Seven Days.Cause Is Under Investigation. Replacement of Detector Assembly W/Higher Temperature Rated Detector to Mitigate Effects to Be Completed by 981019 ML18106A1771997-11-21021 November 1997 Special Rept 97-15,on 971022,2A EDG Declared Inoperable. Caused by Moisture Build Up in Starting Air headers.2A EDG Equipment Inspected Just Subsequent to Aborted Start ML18102B6001997-09-30030 September 1997 Special Rept 97-02:on 970909,isolation of Fire Protection Water to Plant Auxiliary Bldgs & Containments Occurred Due to Closure of Valves 1PF186 & 1PF187.Valves Opened on 970916 & Locally Verified Open by Loss Prevention Personnel ML18102B4241997-06-30030 June 1997 Special Rept 97-01:on 970615,radiation Monitoring Sys Channel 1R15 Was Inoperable for More than Seven Days.Caused by Configuration of Plant.Required Operational Surveillances Will Be Completed on 2R15 & Channel Restored ML18101B3051996-03-25025 March 1996 Special Rept:On 960224,valid Failure of 1B EDG Was Identified During Surveillance Testing.Caused by Fatigue Due to Normal Machine Vibration.Replaced Threaded Nipple ML18101B1581995-12-29029 December 1995 Special Rept 95-02:on 951207,valid Failure of 1A EDG Identified Approx 23 & 1/2 H Into 24 H Endurance Surveillance Test.Caused by Lubricating Oil Leak at Threaded Piping Nipple.Threaded Nipple Replaced ML18101B1541995-12-27027 December 1995 Special Rept 95-001:on 951129,valid Failure of 1B EDG Identified During Routine Monthly Surveillance Test.Caused by Malfunction of Woodward Electronic Governor Control Unit. Unit Replaced & 1B EDG Tested Satisfactorily on 951214 ML18101A8061995-07-0303 July 1995 Special Rept:On 950607,identified That 950601 Failure of EDG 1B Potential Common Mode Failure.Util Unable to Determine Cause at Present Time.Ler Will Be Submitted to NRC ML18101A7341995-05-19019 May 1995 Special Rept:On 950506,RMS Declared Inoperable Due to Problems Encountered W/Operation of Victoreen Met Package. Caused by Met Package Inconsistencies.Appropriate Computer Software Corrections Being Researched & Will Be Implemented ML18101A5601995-02-15015 February 1995 Special Rept 95-01:on 950125,shortly After RCP Turned Off to Remove RCP from Svc,Momentary RCS Pressure Transient Occurred & Pressure Peaked 365.5 Psig Due to Pressure Equalization Through 21 RCS Loop.Procedures Will Be Changed ML18100B0421994-04-27027 April 1994 Special Rept 94-2:on 940329,valid Failure of 1A Diesel Generator Occurred.Caused by Buildup on Contacts of Breaker Position Switch 52HL,resulting in Excessive Electrical Resistance.Breaker Position Switch Replaced ML18100A8271994-01-20020 January 1994 Special Rept 94-01:on 940106,radiation Monitoring Channels 1R45B & 1R45C Declared Inoperable & Exceeded 7-day Time Frame for Restoring Inoperable Channels to Operable Status on 940113.Monitors Returned to Svc on 940118 ML18100A6211993-09-17017 September 1993 Special Rept 93-4:on 930910,radiation Monitoring Channels 2R45B & 2R45C Inoperable Greater than Seven Days.Caused by Design Deficiency.Corrected by Separating Monitors Reference & Chassis Grounds ML18100A4941993-07-21021 July 1993 Special Rept:On 930707,process Monitor - Noble Gas effluent- Condenser Exhaust Sys Was Removed from Svc Due to Observed Water in Its Sample Line.Sample Line 2R15 Drained & Dried. W/930721 Ltr ML18096B3511993-03-23023 March 1993 Special Rept 93-2:on 930310,RMS Channels 2R45B & 2R45C Removed from Svc to Functionally Test Low Flow Differential Pressure.Test Results Showed That Switch Inoperable.Caused by Design Deficiency.Design Mod Being Prepared ML18096B2571993-02-0404 February 1993 Special Rept 93-1:on 930104,fire Barrier Penetration Seal Impaired to Support Welding of RHR Sys Drain Piping.Barrier Inoperable for More than 7 Days.Cables Removed & Access Hatch Closed to Restore Penetration to Operability ML18096B2331993-01-28028 January 1993 Special Rept 93-1:on 930114,RMS Channels 1R45B & 1R45C Declared Inoperable Upon Annuciation of External Fail Alarm.Cause Not Determined.Upon Completion,Corrective Actions Will Be Taken & Channels Will Return to Svc ML18096B1701992-12-21021 December 1992 Special Rept 92-9:on 921208,chilled Water Supply Could Not Be Restored Following Completion of Rms Channel Functional Surveillance.Caused by Blow Indication Panel Circuit Fuse. New Solenoid Valve Operator Ordered ML18096B1601992-12-18018 December 1992 Special Rept 92-9:on 921112,fire Barrier Impairment Initiated to Support Svc Water Sys Design Changes & Penetration Inoperable for More than 7 Days Through 921119. Penetrations Will Be Sealed Upon Completion of Work ML18096B1171992-11-23023 November 1992 Special Rept 92-8:on 921116,RMS Channels Declared Inoperable & Removed from Svc for More than 7 Days.Caused by Bad Ground Wire Connection on Three Wire Power Cable.Connector Repaired & post-maint Testing Successfully Completed ML18096B0861992-11-0505 November 1992 Special Rept 92-7:on 921008,discovered Door Misaligned & Would Not Close & Latch.Caused by Equipment Failure.Fire Door Declared Functional Upon Completion of Repairs & Testing ML18096B0731992-10-30030 October 1992 Special Rept 92-8:on 920924,fire Barrier Penetrations Impaired to Support Design Change Work.On 921001, Penetrations Exceeded seven-day Limit,Per TS 3.7.11.a. Impaired Penetrations Resealed & Inspected ML18096B0591992-10-23023 October 1992 Special Rept 92-6:on 920924,valid Failure,Involving DG 2B, Occurred During Monthly Surveillance Testing & Exhaust Smoke Observed Rising from Around Turbocharger.Caused by Loose Pipe Fasteners.Fasteners Torqued Appropriately ML18096B0021992-09-24024 September 1992 Special Rept 92-7:on 920826,auxiliary Bldg 100-ft Elevation Corridor Fire Door Found Impaired & Not Returned to Operability within 7 Days.Caused by Broken Internal Hinge Plate Welds.Damaged Door Will Be Replaced ML18096A9151992-08-21021 August 1992 Special Rept 92-6:on 920814,radiation Monitoring Channels 1R45B & 1R45C Declared Inoperable for More than 7 Days. Caused by Degradation on Impellers of Two Sample Pumps. Preventive Maint Applicability Review Will Be Performed ML18096A8841992-08-0707 August 1992 Special Rept 92-4-1:on 920430,fire Pump 1 Started Knocking 10 Minutes Into half-hour Run.Caused by sheared-off Follower Guide Pin.On 920514,fire Pump Developed Severe Oil Leak.Caused by Piston Failing to Contact Cylinder Head ML18096A8261992-07-0909 July 1992 Special Rept 92-5:on 920623,actuation Capability of 78-ft Lower Electrical Penetration CO2 Fire Protection Sys Inoperable for More than 14 Days.Caused by Required Maint Work.Sys Returned to Svc on 920702 ML18096A7431992-05-22022 May 1992 Special Rept 92-4:on 920430 & 0514,fire Pumps 1 & 2, Respectively,Inoperable for More than 7 Days.Caused by Sheared Cam Follower Pin & Severe Oil Leak.Fire Protection Sys cross-tie Valve Opened to Provide Backup Protection ML18096A7281992-05-22022 May 1992 Special Rept 92-3,on 920422,discovered That CO2 Sys Was Inoperable.Caused by Maint Work Activities.Upon Completion of Maint Diesel Generator Area CO2 Sys Will Be Returned to Svc ML18096A7351992-05-15015 May 1992 Ro:On 920423,fire Pump 1 Declared Inoperable & Remains Inoperable Due to Broken Crankshaft.Both Fire Suppression Sys Inoperable.On 920515,fire Pump 2 Declared Inoperable Due to Severe Oil Leak.Written Rept to Be Provided in 14 Days ML18096A7021992-05-11011 May 1992 Special Rept 92-2-1:on 920324,0414,15 & 25,fire Barriers Impaired for More than 7 Days to Support Planned Work in SW Sys,Sw Project Support & SW Pipe Replacement.Hourly Fire Watch Will Continue Until All Concerns Resolved ML18096A6501992-04-23023 April 1992 Special Rept 92-2:on 920324,0414 & 15,fire Barriers Impaired for Greater than Seven Days in Support of Planned Work. Hourly Fire Watch Will Continue Until Fire Protection Concerns Associated W/Areas Resolved ML18096A6491992-04-23023 April 1992 Special Rept 92-4:on 920318,two Fire Barrier Penetrations Were Impaired to Support Turbine/Generator Design Change Work for Greater than Seven Days.Caused by Outage Related Activities.Penetrations Were Resealed on 920326 ML18096A6051992-03-26026 March 1992 Special Rept 92-3:on 920302,jacket Water Leakage Developed After Loading DG 2A.On 920305,DG 2A Tripped on Low Lube Oil Pressure.Both Events Caused by Equipment Failure.Tube Connector Compression Fitting Replaced & Diesel Retested ML18096A5891992-03-23023 March 1992 Special Rept 92-2:on 920302 & 21,fire Barriers Impaired for More than 7 Days to Support Design Changes & outage-related Activities.Hourly Fire Watch Established & Fire Penetrations Will Be Sealed ML18096A5671992-03-12012 March 1992 Special Rept 92-1:on 920223,fire Barriers Found Impaired for Greater than Seven Days.Caused by Equipment Failure.Fire Door Will Be Replaced Upon Receipt of New Door ML18096A5101992-02-0606 February 1992 Special Rept 92-1 on 920104,06 & 25,fire Barriers Impaired for Greater than Seven Days in Support of Outage Related Activities Due to Time Required to Complete Work.Hourly Fire Watch Will Continue Until Concerns Re Areas Are Resolved ML18096A4231992-01-0909 January 1992 Special Rept 91-3,on 911210,26 & 27:fire Barriers Found Impaired for Greater than 7 Days.Cause of Occurrence Due to Support Outage Related Activities.Penetrations Will Be Sealed ML18096A4001991-12-23023 December 1991 Special Rept 91-4 Re Valid Failure of Diesel Generator 2B on 911122.Cause Unknown.Surveillance Procedure SP(O)4.8.1.1.2 Performed Satisfactorily ML18096A2301991-08-22022 August 1991 Special Rept 91-02:on 910725,reactor Trip Breaker Failure Occurred Duing Surveillance Testing of Reactor Trip Bypass Breaker.Detailed Investigation Rept Being Prepared & Breaker Being Replaced ML18096A0841991-06-20020 June 1991 Special Rept:On 910523 & 910525,valid Failure Re 2B Diesel Generator Occurred When pre-lube Pump Heater Circuit de-energized & non-valid Failure Occurred on 910525 Re Jacket Water Leak ML18095A8901991-04-17017 April 1991 Special Rept 91-1-1:on 910218,910220,910224 & 910322 Fire Barrier Penetration Seals Impaired for Greater than Seven Days.Cause of Impairment Was to Support Outage Activities. Hourly Fire Watch Will continue.W/910417 Ltr ML18095A8111991-03-20020 March 1991 Special Rept:On 910211,910213 & 910217 Fire Barrier Impairments Greater than Seven Days in Support of Planned Work.Cause of Impairment of Fire Barrier Penetrations Was to Support Outage Related Activities ML18095A7831991-03-0707 March 1991 Special Rept 91-1:on 910211,Elevation 64 & 84 Ft Switchgear Rooms & Elevation 78 Ft Electrical Penetration Area CO2 Fire Protection Sys Inoperable for More than 14 Days.Caused by Required Design Work.Continuous Fire Watch Established ML18095A7521991-02-20020 February 1991 Special Rept 88-3-28:from 880720-910122,listed Fire Barrier Penetration Seal Impairments Occurred.Cause Not Positively Determined.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18095A6751990-12-26026 December 1990 Special Rept 90-7:on 901210,switchgear Rooms & Electrical Penetration Area CO2 Fire Protection Sys Inoperable for More than 14 Days to Support Design Change Work on 901126. Adequate Precautions Taken to Ensure Design Capability ML18095A7511990-12-0505 December 1990 Revised Special Rept 90-10-1:on 900707,TS Action Statement 3.7.10.3c.a Entered When 64 Ft & 84 Ft Elevation Switchgear Room CO2 Fire Protection Sys Declared Inoperable.Caused by Equipment Failure.Sys Design Drawing Revised ML18095A6141990-11-14014 November 1990 Special Rept 90-06:on 901022 & 24,fire Barriers Penetration Seals Impaired for More than Seven Days.Caused by Support Design Change Work.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18095A5801990-11-0707 November 1990 Supplemental Special Rept 88-3-27:on 880720-901010,listed Fire Barriers Impaired for More than 7 Days.Cause of Degraded Fire Barrier Penetrations Could Not Be Positively Determined 1998-08-31
[Table view] Category:LER)
MONTHYEARML18106A9621998-11-16016 November 1998 Special Rept:On 981006,train B of Reactor Vessel Level Indicating Sys Was Indicating Malfunction.Caused by Loss of Fill in Capillary Sensing Line.Extensive Troubleshooting Was Performed on Sys ML18106A8591998-08-31031 August 1998 Special Rept:On 980816,RMS Channel 1R15 Inoperable for Greater than Seven Days.Cause Is Under Investigation. Replacement of Detector Assembly W/Higher Temperature Rated Detector to Mitigate Effects to Be Completed by 981019 ML18106A1771997-11-21021 November 1997 Special Rept 97-15,on 971022,2A EDG Declared Inoperable. Caused by Moisture Build Up in Starting Air headers.2A EDG Equipment Inspected Just Subsequent to Aborted Start ML18102B6001997-09-30030 September 1997 Special Rept 97-02:on 970909,isolation of Fire Protection Water to Plant Auxiliary Bldgs & Containments Occurred Due to Closure of Valves 1PF186 & 1PF187.Valves Opened on 970916 & Locally Verified Open by Loss Prevention Personnel ML18102B4241997-06-30030 June 1997 Special Rept 97-01:on 970615,radiation Monitoring Sys Channel 1R15 Was Inoperable for More than Seven Days.Caused by Configuration of Plant.Required Operational Surveillances Will Be Completed on 2R15 & Channel Restored ML18101B3051996-03-25025 March 1996 Special Rept:On 960224,valid Failure of 1B EDG Was Identified During Surveillance Testing.Caused by Fatigue Due to Normal Machine Vibration.Replaced Threaded Nipple ML18101B1581995-12-29029 December 1995 Special Rept 95-02:on 951207,valid Failure of 1A EDG Identified Approx 23 & 1/2 H Into 24 H Endurance Surveillance Test.Caused by Lubricating Oil Leak at Threaded Piping Nipple.Threaded Nipple Replaced ML18101B1541995-12-27027 December 1995 Special Rept 95-001:on 951129,valid Failure of 1B EDG Identified During Routine Monthly Surveillance Test.Caused by Malfunction of Woodward Electronic Governor Control Unit. Unit Replaced & 1B EDG Tested Satisfactorily on 951214 ML18101A8061995-07-0303 July 1995 Special Rept:On 950607,identified That 950601 Failure of EDG 1B Potential Common Mode Failure.Util Unable to Determine Cause at Present Time.Ler Will Be Submitted to NRC ML18101A7341995-05-19019 May 1995 Special Rept:On 950506,RMS Declared Inoperable Due to Problems Encountered W/Operation of Victoreen Met Package. Caused by Met Package Inconsistencies.Appropriate Computer Software Corrections Being Researched & Will Be Implemented ML18101A5601995-02-15015 February 1995 Special Rept 95-01:on 950125,shortly After RCP Turned Off to Remove RCP from Svc,Momentary RCS Pressure Transient Occurred & Pressure Peaked 365.5 Psig Due to Pressure Equalization Through 21 RCS Loop.Procedures Will Be Changed ML18100B0421994-04-27027 April 1994 Special Rept 94-2:on 940329,valid Failure of 1A Diesel Generator Occurred.Caused by Buildup on Contacts of Breaker Position Switch 52HL,resulting in Excessive Electrical Resistance.Breaker Position Switch Replaced ML18100A8271994-01-20020 January 1994 Special Rept 94-01:on 940106,radiation Monitoring Channels 1R45B & 1R45C Declared Inoperable & Exceeded 7-day Time Frame for Restoring Inoperable Channels to Operable Status on 940113.Monitors Returned to Svc on 940118 ML18100A6211993-09-17017 September 1993 Special Rept 93-4:on 930910,radiation Monitoring Channels 2R45B & 2R45C Inoperable Greater than Seven Days.Caused by Design Deficiency.Corrected by Separating Monitors Reference & Chassis Grounds ML18100A4941993-07-21021 July 1993 Special Rept:On 930707,process Monitor - Noble Gas effluent- Condenser Exhaust Sys Was Removed from Svc Due to Observed Water in Its Sample Line.Sample Line 2R15 Drained & Dried. W/930721 Ltr ML18096B3511993-03-23023 March 1993 Special Rept 93-2:on 930310,RMS Channels 2R45B & 2R45C Removed from Svc to Functionally Test Low Flow Differential Pressure.Test Results Showed That Switch Inoperable.Caused by Design Deficiency.Design Mod Being Prepared ML18096B2571993-02-0404 February 1993 Special Rept 93-1:on 930104,fire Barrier Penetration Seal Impaired to Support Welding of RHR Sys Drain Piping.Barrier Inoperable for More than 7 Days.Cables Removed & Access Hatch Closed to Restore Penetration to Operability ML18096B2331993-01-28028 January 1993 Special Rept 93-1:on 930114,RMS Channels 1R45B & 1R45C Declared Inoperable Upon Annuciation of External Fail Alarm.Cause Not Determined.Upon Completion,Corrective Actions Will Be Taken & Channels Will Return to Svc ML18096B1701992-12-21021 December 1992 Special Rept 92-9:on 921208,chilled Water Supply Could Not Be Restored Following Completion of Rms Channel Functional Surveillance.Caused by Blow Indication Panel Circuit Fuse. New Solenoid Valve Operator Ordered ML18096B1601992-12-18018 December 1992 Special Rept 92-9:on 921112,fire Barrier Impairment Initiated to Support Svc Water Sys Design Changes & Penetration Inoperable for More than 7 Days Through 921119. Penetrations Will Be Sealed Upon Completion of Work ML18096B1171992-11-23023 November 1992 Special Rept 92-8:on 921116,RMS Channels Declared Inoperable & Removed from Svc for More than 7 Days.Caused by Bad Ground Wire Connection on Three Wire Power Cable.Connector Repaired & post-maint Testing Successfully Completed ML18096B0861992-11-0505 November 1992 Special Rept 92-7:on 921008,discovered Door Misaligned & Would Not Close & Latch.Caused by Equipment Failure.Fire Door Declared Functional Upon Completion of Repairs & Testing ML18096B0731992-10-30030 October 1992 Special Rept 92-8:on 920924,fire Barrier Penetrations Impaired to Support Design Change Work.On 921001, Penetrations Exceeded seven-day Limit,Per TS 3.7.11.a. Impaired Penetrations Resealed & Inspected ML18096B0591992-10-23023 October 1992 Special Rept 92-6:on 920924,valid Failure,Involving DG 2B, Occurred During Monthly Surveillance Testing & Exhaust Smoke Observed Rising from Around Turbocharger.Caused by Loose Pipe Fasteners.Fasteners Torqued Appropriately ML18096B0021992-09-24024 September 1992 Special Rept 92-7:on 920826,auxiliary Bldg 100-ft Elevation Corridor Fire Door Found Impaired & Not Returned to Operability within 7 Days.Caused by Broken Internal Hinge Plate Welds.Damaged Door Will Be Replaced ML18096A9151992-08-21021 August 1992 Special Rept 92-6:on 920814,radiation Monitoring Channels 1R45B & 1R45C Declared Inoperable for More than 7 Days. Caused by Degradation on Impellers of Two Sample Pumps. Preventive Maint Applicability Review Will Be Performed ML18096A8841992-08-0707 August 1992 Special Rept 92-4-1:on 920430,fire Pump 1 Started Knocking 10 Minutes Into half-hour Run.Caused by sheared-off Follower Guide Pin.On 920514,fire Pump Developed Severe Oil Leak.Caused by Piston Failing to Contact Cylinder Head ML18096A8261992-07-0909 July 1992 Special Rept 92-5:on 920623,actuation Capability of 78-ft Lower Electrical Penetration CO2 Fire Protection Sys Inoperable for More than 14 Days.Caused by Required Maint Work.Sys Returned to Svc on 920702 ML18096A7431992-05-22022 May 1992 Special Rept 92-4:on 920430 & 0514,fire Pumps 1 & 2, Respectively,Inoperable for More than 7 Days.Caused by Sheared Cam Follower Pin & Severe Oil Leak.Fire Protection Sys cross-tie Valve Opened to Provide Backup Protection ML18096A7281992-05-22022 May 1992 Special Rept 92-3,on 920422,discovered That CO2 Sys Was Inoperable.Caused by Maint Work Activities.Upon Completion of Maint Diesel Generator Area CO2 Sys Will Be Returned to Svc ML18096A7351992-05-15015 May 1992 Ro:On 920423,fire Pump 1 Declared Inoperable & Remains Inoperable Due to Broken Crankshaft.Both Fire Suppression Sys Inoperable.On 920515,fire Pump 2 Declared Inoperable Due to Severe Oil Leak.Written Rept to Be Provided in 14 Days ML18096A7021992-05-11011 May 1992 Special Rept 92-2-1:on 920324,0414,15 & 25,fire Barriers Impaired for More than 7 Days to Support Planned Work in SW Sys,Sw Project Support & SW Pipe Replacement.Hourly Fire Watch Will Continue Until All Concerns Resolved ML18096A6501992-04-23023 April 1992 Special Rept 92-2:on 920324,0414 & 15,fire Barriers Impaired for Greater than Seven Days in Support of Planned Work. Hourly Fire Watch Will Continue Until Fire Protection Concerns Associated W/Areas Resolved ML18096A6491992-04-23023 April 1992 Special Rept 92-4:on 920318,two Fire Barrier Penetrations Were Impaired to Support Turbine/Generator Design Change Work for Greater than Seven Days.Caused by Outage Related Activities.Penetrations Were Resealed on 920326 ML18096A6051992-03-26026 March 1992 Special Rept 92-3:on 920302,jacket Water Leakage Developed After Loading DG 2A.On 920305,DG 2A Tripped on Low Lube Oil Pressure.Both Events Caused by Equipment Failure.Tube Connector Compression Fitting Replaced & Diesel Retested ML18096A5891992-03-23023 March 1992 Special Rept 92-2:on 920302 & 21,fire Barriers Impaired for More than 7 Days to Support Design Changes & outage-related Activities.Hourly Fire Watch Established & Fire Penetrations Will Be Sealed ML18096A5671992-03-12012 March 1992 Special Rept 92-1:on 920223,fire Barriers Found Impaired for Greater than Seven Days.Caused by Equipment Failure.Fire Door Will Be Replaced Upon Receipt of New Door ML18096A5101992-02-0606 February 1992 Special Rept 92-1 on 920104,06 & 25,fire Barriers Impaired for Greater than Seven Days in Support of Outage Related Activities Due to Time Required to Complete Work.Hourly Fire Watch Will Continue Until Concerns Re Areas Are Resolved ML18096A4231992-01-0909 January 1992 Special Rept 91-3,on 911210,26 & 27:fire Barriers Found Impaired for Greater than 7 Days.Cause of Occurrence Due to Support Outage Related Activities.Penetrations Will Be Sealed ML18096A4001991-12-23023 December 1991 Special Rept 91-4 Re Valid Failure of Diesel Generator 2B on 911122.Cause Unknown.Surveillance Procedure SP(O)4.8.1.1.2 Performed Satisfactorily ML18096A2301991-08-22022 August 1991 Special Rept 91-02:on 910725,reactor Trip Breaker Failure Occurred Duing Surveillance Testing of Reactor Trip Bypass Breaker.Detailed Investigation Rept Being Prepared & Breaker Being Replaced ML18096A0841991-06-20020 June 1991 Special Rept:On 910523 & 910525,valid Failure Re 2B Diesel Generator Occurred When pre-lube Pump Heater Circuit de-energized & non-valid Failure Occurred on 910525 Re Jacket Water Leak ML18095A8901991-04-17017 April 1991 Special Rept 91-1-1:on 910218,910220,910224 & 910322 Fire Barrier Penetration Seals Impaired for Greater than Seven Days.Cause of Impairment Was to Support Outage Activities. Hourly Fire Watch Will continue.W/910417 Ltr ML18095A8111991-03-20020 March 1991 Special Rept:On 910211,910213 & 910217 Fire Barrier Impairments Greater than Seven Days in Support of Planned Work.Cause of Impairment of Fire Barrier Penetrations Was to Support Outage Related Activities ML18095A7831991-03-0707 March 1991 Special Rept 91-1:on 910211,Elevation 64 & 84 Ft Switchgear Rooms & Elevation 78 Ft Electrical Penetration Area CO2 Fire Protection Sys Inoperable for More than 14 Days.Caused by Required Design Work.Continuous Fire Watch Established ML18095A7521991-02-20020 February 1991 Special Rept 88-3-28:from 880720-910122,listed Fire Barrier Penetration Seal Impairments Occurred.Cause Not Positively Determined.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18095A6751990-12-26026 December 1990 Special Rept 90-7:on 901210,switchgear Rooms & Electrical Penetration Area CO2 Fire Protection Sys Inoperable for More than 14 Days to Support Design Change Work on 901126. Adequate Precautions Taken to Ensure Design Capability ML18095A7511990-12-0505 December 1990 Revised Special Rept 90-10-1:on 900707,TS Action Statement 3.7.10.3c.a Entered When 64 Ft & 84 Ft Elevation Switchgear Room CO2 Fire Protection Sys Declared Inoperable.Caused by Equipment Failure.Sys Design Drawing Revised ML18095A6141990-11-14014 November 1990 Special Rept 90-06:on 901022 & 24,fire Barriers Penetration Seals Impaired for More than Seven Days.Caused by Support Design Change Work.Hourly Fire Watch Will Continue Until All Fire Protection Concerns Resolved ML18095A5801990-11-0707 November 1990 Supplemental Special Rept 88-3-27:on 880720-901010,listed Fire Barriers Impaired for More than 7 Days.Cause of Degraded Fire Barrier Penetrations Could Not Be Positively Determined 1998-08-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
[Table view] |
Text
PS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station August 7, 1990 U. s. Nuclear Regulatory Commission.
Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 SUPPLEMENTAL SPECIAL REPORT 88-3-24 This supplemental Special Report addresses additional fire barrier penetration seal impairments (for both Salem Unit 1 and Salem Unit
- 2) which have not been restored to functional status within seven (7) days. These impairments have been identified by the Penetration Seal Task Force. This report has been prepared in accordance with the reporting requirements of Technical Specification Action Statement 3.7.11.a pursuant to Technical Specification 6.9~2.
Sincerely yours,
~~&ljpzhfi~
General Manager -
Salem Operations MJP:pc Distribution 900814006~ ?Q9~9Z~~
U~UUUL!L pnp s- .ADOCK PDC The En*.H*gy People
UNIT. 1 SPECIAL REPORT 8*3-24 PLANT IDENTIFICATION:
Salem Generating Station - Units 1 & 2 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Technical Specification 3.7.11; Fire Barriers Impaired For Greater Than 7 Days Event Date(s): 7/20/88, S/9/88, 9/7/88, 10/11/88,* 11/7/88, 12/7/88, 1/5/89, ~/6/89, 3/7/89, 4/6/89, 5/9/89, 6/7/89, 7/12/89, 8/8/89, 9/7/89, 10/7/89, 11/8/89, 12/8/89, 1/9/90, 2/8/90, 3/14/90, 4/9/90, 5/8/90, 6/8/90, 7/16/90 Report Date: 8/7/90 This report was initiated by Incident Report Nos.88-268, 88-531,88-536, 88-537,88-544, 89-050,89-075, 89-086,89-091, B9-092, 89:_127,89-287, 89-349, 472,90-357, and 90-359 .
.CONDITIONS PRIOR TO OCCURRENCE:
N/A DESCRIPTION OF OCCURRENCE:
As identified in PSE&G letter NLR-N88037 dated March 4, 1988, PSE&G has iriitiated a comprehensive review/inspection of fire barrier penetration seals. Due to the-additional review by the Penetration Seal Task Force; penetrations found impaired are not being repaired within seven days as specified by Technical Specification Action Statement 3.7.11.a. This report summarizes the task force findings and Technical Specification 4.7.11 surveillance activity findings associated with inadequate penetration seals for both Unit 1 and Unit
- 2. T_he inadequate penetration seals found, to the date of issue of this report, include:
On July 13, 1988 two fire Barrier cable penetratibn were found degraded. The penetration contained electrical sleeving containing an electrical cable surrounded by foam type fire sealant. The area (approximately 1/8" gap and 1/4" gap respectively) surrounding the electrical sleeves were not sealed thereby constituting an impaired seal. The fire barrier is in the east wall of the 100' Elevation Re1ay Room.
On July 25, 1988 three (3) degraded fire barrier cable penetration seals were found on the south wall in the*lOO' Elevation Relay Room. Two (2) of these penetrations are 3" in diameter and the other is 5.5" (located -1a feet above*~he floor). The 3" penetrations contain fire wrapped cabling. This fire wrap extends over the penetration. There is no foam behind the fire wrap.
- It provides a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rated barrier, .however, the wall is a 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> barrier. The 5.5" penetration contains a 4" conduit surrounded by foam. The foam contains an 1/8" gap at the base of the conduit.
Unit 1 SPECIAL REPORT 8*-24 -2~
DESCRIPTION OF OCCURRENCE: (cont'd)
On July 28, 1988 one (1) 3.5" degraded fire barrier cable penetration seal was found on the north wall in the 100' Elevation Relay Room. The pe:netration contains cabling surrounded by foam. The foam contains an 1/2" diameter hole.
Between August 2, 1988 and August 301 1988, 138 additional penetration seals were found impaired*of which 134 penetrations are located in the Unit 1 Relay Room and 4 penetrations are located in the Unit 1 lA 125 V Battery . Room . . The penetrations range in size from -3 inches to -6 inches in diameter. The nature of the impairments include 6 with no seal, 14 with a hole in the seal (unknown cause), 2 with foreign material imbedded in the seal (one imbedded with a rag and the other with duct tape).,
30 with a void in th.e seal (due to inadequate quantity.of foam injection upon installation) , 6 with apparent degrada"tion *(e.g. r cable pulled through) 47 with inadequate color/cell structure (reference LER 272/88-013-00) and 32 that are not deep enough into the penetration per design (less than 6 inches).
Between August 31, 1988 and July 30, 1990, 6914 Unit 1 penetration seals and 5185 Unit 2 penetration seals were reviewed. Of these, 2857 penetration seals were determined to be impaired~ The majority of penetrations range in size from -3 inches to -Q inches in diameter. There were 336 penetrations which were larger than 6 inches in. diameter .. These penetrations ranged from 3"x5" to 258"x36".
- Page 3 of this report contains ~ table of the penetration seals found impaired, between August 2, 1988 ~nd July 30, 1990, *in.
relation to the fire zone where they were found. The impairment designator terms include:
No Seal NOS Hole in Seal HOL Void in Seal VIS Depth Not Great Enough DPT Color/Cell Structure CEL Seal Degradation DEG Foreign Material Imbedded FMT Planned Impairment PIM An hourly fire watch patrol had been established for the above areas previously due to other fire protection concerns. Therefore, the requirements of Tech. Spec. Action Statement 3.7.11.a are met.
Unit 1 Technical Specification 3.7.11 states:
"All fire penetrations (includirig cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting safety related areas shall be fuhctional."
.*Unit 1 Technical Specification Action Statement 3. 7 .11. a states:
"With one or more of the above required fire barrier penetrations non-functional, within one hour either establish a
UNIT 1 SPECIAL REPORT ~3-24 DESCRIPTION OF OCCURRENCE: (cont'd) continuous fire watch on at least one ~ide of the affected penetration, o~ verify the OPERABILITY of fire detectors on at least one side of the non-functi9nal- fire barrier and establish ari hourly fire watch patrol. Restore the nqn-functional fire barrier penetration(s) to functional status within 1 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the. next 30 days outlining the action taken, the cause of the non-functional penetration and plans and schedule for restoring the fire barrier penetration(s) to functional status."
NOTE - Unit 1 Technical Specification 3.7.11 4iffers from Unit 2. The words "functional" and "non-functional" are replaced by the words
TABLE OF INOPERABLE PENETRATION SEALS 8/02/88 - 7/30/90 AREA NOS HOL DPT CEL ,DEG PIM U-1 Relay Room 15 34 54 72 194 7 *3 l**
U-1 lA DIG Control Room 2 3 2 21 U-1 lB DIG Control Room 1 1 3 21 2 U-:-1 lC D/G Control Room 1- 1 1 11 11 2 U-1 lA 125 v Battery Room 2 3~
2 U-1 lC 125 v Battery Room 20 1 1 U-1 #1 250 v Battery Room 1 1 5 U-1 #3 Stairwell 13 1 5 U-1 64' Elevation, Aisle 3 1 6 17
- 1 Auxiliary Building U-1 84' Elevation, Aisle 6 4 7 7 1
- 1 Auxiliary Building U-1 122' Elevation; N2 1 1 Bottle Storage Area U-1 84' Corridor; Unit 1 &: 3 3 2 Common East &: West
- U-1 78' Electrical Penetra. 1 1 1 1 7 Area U-1 100' Boric Acid Transfer 3 4 12 5 Pump Area ..
UNIT 1 SPECIAL REPORT 8*-24 TABLE OF INOPERABLE PENETRATION SEALS (cont'd) 8/02/88 - 7/30/90
.AREA NOS HOL VIS DPT CEL DEG FMT PIM U-1 100' El. Mechanical 1 5 2 8 3 1 Penetration Area - Blowdown Tanks U-1 100' El. Corridor 2 3 3 2 1 Service Building U-1 100' Elevation, Aisle 4 4 2 6 14 1
- 1 Auxiliary Building U-1 100' Corridor; Unit 1 & 15 11 8 30 61 1 2* Common East & West
- U-1 84' Corridor; Unit 1 & 2 7 14 11 2 1 2 Common North & South U-1 84' Corridor; Unit 1 & 3 3 2 Common East & West
- U-1 122' Lobby 2 U-1 100' Lobby 1 1 U-1 64' Lobby 1 u-1 11/12 Containment Spray 4 4 6 19 2 Pumps & Spray Add. Tank Area U-1 100' Corridor; Unit 1 & 2 4 3 1 185 2 2 Common North & South U-1 100' Elevation Counting 6 1 1 Room U-1 #11 Diesel Oil Tk Room 1 1 3 U-1 #12 Diesel Oil Tk Room 2 5 U-1 84' Elev. Control Area 23 14 1 22 91 1
- 1 Transformer Bus Rm.
u.:..1 Spent Fuel Pit Heat 3 3 6 16 Exchanger & Pump Area U-1 lA Diesel Generator Area 5 1 1 U-1 lB Diesel Generator Area 1 1 7 1 7 U-1 le Diesel Generator Area 4 1 2 3 U-1 Waste Evaporator Room 4 11 4 1 1 U-1 100' Elevation Mechanical 8 4 10 Penetration Area
UNIT 1 SPECIAL REPORT 8*-24 TABLE OF INOPERABLE PENETRATION SEALS (cont'd) 8/02/88 -. 7/30/90 VIS DPT CEL U-1 UPS Battery Room 2 U-1 Containment Rad Mon Room 4 1 *10 10 U-1 #11 Chg. & SI Pump Room 1 4 U-1 #12 Chg *. & SI Pump Room 1 U-1 #13 Chg. & SI Pump Room- 2 U-1 84' El. Pipe Trench 126 1 1 16 . 2*
U-1 100' El. Baling & Storage 7 1 3 1 1 U-1 110' El. Control Console 1 9 U-1 78' El. Contain. Rad 1 1 Mon. Room U-1 84' El. #11 Comp. Cool. 20 1 3 .2 Heat Xgr. & 12 CC Pp Room U-1 100' Elec. Penetra. Area 14 4 17 6 5 U-1 Laundry, Chem Pump Area 5 3 2 19 4 U-1 ~4' El. Coritrol Area #1 3 4 18 11 1 4KV Bus U-i #1 Letdown Heat Exch. 1 U-1 84~ El. #12 Comp. Cool. 3 3 *3 Heat Xgr. & 12 & 13 CC Pp Room U-1 #11 SI Pump Room 1 1 U-1 Pipe Trench 14 3 3 20 16 3 U-1 Rx Coolant Filter Area 9 1 U-1 84' Spent Resin Xfer Pp Rm 2 V-1 11 & 12 Mon. Tank Room 8 1 5 2 U-1 84' Elevator Lobby 1 U-1 Aux Feed Pumps 3 U-1 Valve Alley 3 2 3 U-1 Seal Water Heat XChg 2 3 1 U~l 84' El. Corridor 2 2 1
UNIT 1 SPECIAL REPORT 8At-24 e TABLE OF INOPERABLE PENETRATION SEALS (cont'd) 8/02/88 - 7/30/90 AREA NOS HOL VIS DPT CEL DEG FMT PIM U-1 A/C & Boric Acid 5 1 10 81 1 Tank Room U-1 A/C Equipment Rm 1 2 4 U-1 Boric Acid Evap. & 2 1 3 1 Gas Stripper Unit u..,...1 Water Recirc Heater 3 1 1 2 U-1 #1 Stairwell 6 5 U-1 #1 Cone. Filter Area 1 U-1 Rm Next To #11 Chg Pp 2 2 U-1 Diesel Oil C02 Area 4 1 U-1 Motor Control Center 2 1 1 U-1 Elevator - El 2 1 1 U-1 N2 Bottle Storage 3 U-1 #12 RHR XGR Room 1 U-1 55' El. Walkway 2 U-1 Future Mixed Bed 7 Demin U-1 #11 Mixed Bed Demin 2 u-1 #1 Cation Bed (NW) 2 U-1 #1 Cation Bed (SW) 8 U-1 #11 Debora ting Deroin 3 U-1 #12 Debora ting Demin 2 1 U-1* Primary Sampling Lab 3 1 U-1 78' Piping Penetration 1 4 U-1 Vent Duct Shaft 1 6 U-1 Valve Room 4 U-1 Waste Evaporator Area 1 U-1 #11 Evap. Feed Ion Xchg. 3
UNIT 1 SPECIAL REPORT 8At-24 TABLE OF INOPERABLE PENETRATION SEALS (cont'd) 8/02/88 - 7/30/90 AREA NOS HOL VIS DPT CEL JJEG FMT PIM U-1 #12 Evap. Feed Ion Xchg. 2 u:.....1 #13 Evap. Feed Ion Xchg. 4 U-1 #14 Evap. Feed Ion Xchg. 1 1 U-1 100' Aisle #1 N & s 2 U-:-1 122' Corridor 1 U-1 Ops . File & Ref Rm 1 U-1 Watch.Engineer Room 3 u--1 #1 Maint, Spare & Test 1 Equipment Room U-1 #2 Maint,. Spare & Test 2 Equipment Room U-1 Janitors Closet 1 .'
U-1 #1 Control Equip. Room 15 5 U-1 84' El. Pipe Alley 2 3 1 u:...1 Sample Room 1 U-1 Data Logging Rodin 2 16 U-1 Work Control Center 1 2 1 U-1 #11 & #12 RHR Sump Pumps 1 Room U-1 #1 Control Room 4 2 U-1 AC Equip. Room 1 2 U-1 #1 Sp~nt Fuel Pit Filter 1.
U-1 Women's Toilet 5 U-1 Containment Rad Monitor 1 Room U-2 #5 Stairwell 3 1 U-2 #4 Stairwell 7 1 1 U-2 #2 Stairwell 7 1 1
UNIT 1 SPECIAL REPORT 88--24 e TABLE OF INOPERABLE PENETRATION SEALS (cont'd) 8102188 - 1130190 AREA NOS HOL. VIS* DPT CEL DEG FMT PIM U-:-2 100' El. Mechanical Pene. 2 6 Area - Blowdown Tanks U-2 100' El. Corridor. 2 1 U-2 100' Elevatiori Mechani6al 5 3 5 6 4 3 Penetration Area U-2 AC & Bo;ric Acid Tank Room 9 9 21 4. 1 U-2 Relay Room 23 27 4 61 132 1 U-2 22 RHR Xgr Room 3 U-2 84' Control Area Trans- 17 34 4 39 31 former Bus Room
..U-2 Rad. Detector Panel 1 U-2 Battery Room 2C 125VDC 13 U-2 Battery Room 2B 125VDC 2 3 3 U-2 #2 250V Battery Room 3 U-2 Control Area #7 4KV 4 5 2 j 1 Vital Bus Area U-2 110' El. Control Console 1 3 U-2 78' Electrical Pen. Area 5 4 U~2 100' Electrical Pen. Area 2 1 3 U-2 2A DIG Control Room 1 5 4 1*
U-2 2B DIG C_ontrol Room 1 2 11 4 U-2 2C DIG Control Room 2 4 3 U-2 #21 Diesel Oil Tank Area 5 2 1 3 U-2 #22 Diesel Oil Tank Area 1 3 2 4 4 U-2 #21 Diesel Fuel Oil 1 1 Transfer Pump Area U-2 #22 Diesel Fuel Oil 1 Transfer Pump Area U-2 111' Vent. Equip. Area 19 4 ,9
UNIT 1 SPECIAL REPORT 88--24 TABLE OF INOPERABLE PENETRATION SEALS (cont'd) 8/02/88 - 7/30/90 AREA NOS HOL. VIS DPT CEL DEG FMT PIM U-2 100' Vent Duct Shaft 1 1 U-2 64' Storage Area 2 1 19 6 U-2 s*4
- Spent Fuel Pit Heat 4 1 4 XChgr. & Pump Room U-2 Boric Acid XFer Pump Area 9 1 1 2 U-2 Aisle #1 East Section 7 1 1 '2 U-2 Aux. Feedwater Pumps 2 4 *1.
U-2 #21 & 22 Monitor Tank 3 1 1 2 Area U-2 21 & 22 Cont. Spray 11 4 1 1 Pumps & Spray Add Tank U-2 Aisle 2 East & West 1 1 U-2 Counting Room 1 5 U-2 #2 Control Room 13 7 2 1 1*
U-2 78' Containment Rad 6 5 Monitor Room U-2 21 & 22 SI Pump Room 1
- U-2 84' Piping Pene Area 5 U-2 Aisle 2 North & South 1 1 U-2 84' Corridor 1 U~2 Calibration Room 1 U-2 #21 Component Cooling 16 1 Heat Exchanger and Pumps U-2* #22 Component Cooling 6 Heat Exchanger and Pumps U-2 84' SW Piping Room 1 U-2 C02 Fire Equipment Area 1 U-2 Concentrates Holding Tank 1 U-2 Seal Water Heat XChgr 1
UNIT 1 SPECIAL REPORT 8~-24 TABLE OF INOPERABLE PENETRATION SEALS (cont'd) 8/02/88 - .7/30/90 DPT CEL DEG FMT U-2 #2 Rx Coolant Filter Area 7 U-2 #2 Control Equip Room 1 4 U-2 84' Valve Room* 5 U-2 #100 Rad Detector Panel 1 1 u~2 Waste Evaporator Area 1 3 U-2 Vent Duct Enclosure Shaft
-U-2 Motor Control Center 1 U-2 Ref. Water Purifier Room 2 U-2 Data Logging Room 5 7 U-2 A/C Equipment Room 2 U-2 84' Pipe Alley 6 1
~.
U-2 N2 Bottle Storage Area 1 1 U-2 #24 Evap. Feed Ion Xchgr 1 U-2 100' Cation Bed Demin. 3 U-2 8.4 I Valve Alley 1
- - The opposite*room for :the north and east walls is.the Unit 2 Relay Room.
- - The Relay Room PIM was resealed thirteen days after _opening
. APPARENT CAUSE OF OCCURRENCE:
The cause of the degraded fire barrier penetrations _could not be positively determined.
The east wall penetrations (discovered 7/13/88) from the Relay Room side "appeared" sealed visually due tQ the use of* a bushing o~ the sleeve which hid the gap. The 3.5" south wall penetrations (discovered 7/25/88) also appeared sealed from the Relay Room side, as described in the Description of Occurrence section. Closer inspection, as required by. the Seal Penetration Review Group procedures, revealed the nature of the impairments. Technical Specification Surveillance 4~7.11 requires verification of the functional status of fire bar~ier penetrations every eighteen.months via a visual inspection. This inspection would not necessarily identify the non-functional status of the subject penetrations.
UNIT 1 SPECIAL REPORT 88.-24 APPARENT CAUSE OF OCCURRENCE: (cont'd)
The 5.~" south wall penetration (found July 25) is located in a difficult to reach location. The gap in the seal may have formed due to shrinkage. It does not appear as though a cable was ~ulled (forming the gap) .
The 3.5" north wall penetration (found July 28) is .also located in a difficult to reach location. The gap in the seal a~pears to have formed as a result of a cable pull. It has not been determined when or by whom the cable was pulled.
The penetrations with non-functional seals, found between August 2, 1988 and July 30, 1990, are similar in configuration (except as noted) to the penetrations identified in the original issue .of this Special Report. The cause of their degraded condition also could not positively be determined.
ANALYSIS OF OCCURRENCE:
The functional integrity of the penetration fire. barriers ensures that fires will be confined or adequately retarded from spreading to adjacent p9rtions of the facility. This design feature minimizes the possibility of a single fire involving several areas *of the facility.
The fire barrier* penetration* seals are a passive element in the facility fire protectiort program
- and are subject to periodic ..
- inspections. This report satisfi~s the repoiting ~equirements of Technical Specification 3. 7 .11. a pursuant. to . Technical Specification 6.9.2 since the time between discovery ~nd eventual repair of the fire barrier impairments is greater than seven (7) days.* Appropriate actions were already in place.in accordance with the requirements of Technical Specification Action Statement 3.7.11.a to establish a one hour roving fire watch for the impaired fire barriers once the impairments were identified.
The subject fire area contains detection in addition to the.roving fire watch patrol. Therefore, it is re~sonable to.assume that a fire in either area would be detected before it could involve an adjacent area. *This occur~ence ther~fore involved no undue ~isk to the health or safety of the public.
CORRECTIVE ACTION:
The hourly fire watch, as addressed in the
Description:
of Occurrence section, will continue until all fire protection concerns associated with these areas are resolved.
- The repair of the penetrations was not accomplished within seven (7) days due to the additional review beirig conducted by th~ Penetration Seal Task Force. Upon completion of this review the penetrations will be sealed.
Penetration seal repair work has been initiated. The Unit 1 Relay Room was the first area worked. To date, 3241 penetrations have been sealed and accepted by ~he Penetration Seal Task Force.
The majority of those penetrations in the Unit 1 and.Unit 2 Relay Rooms (halon discharge areas) which either have no seal or holes **
UNIT 1 SPECIAL REPORT 88.-24 CORRECTIVE ACTION: (cont'd) -
through the seal have been sealed using approved station procedure M3Y, "Installation and Repair of Fire Barrier and Flood Protection Seals".
The review and corrective actions, conducted by the Penetration Seal Review Program, will be completed in accordance with the March 4, 1988 PSE&G letter NLR-N88037 to the NRC, the August 26, 1988 .
telecommunication between PSE&G and the NRC Region 1 office, and the August 15, 1989 semi-annual management meeting conducted with the NRC.
o/c:fWoL~ /:~.d General Manager - /,£ >--U Salem Operations MJP:pc SORC Mtg.90-100