|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18065B1151997-12-0909 December 1997 LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability ML18067A7751997-11-11011 November 1997 LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved ML18067A7581997-10-30030 October 1997 LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation ML18067A7461997-10-23023 October 1997 LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure. ML18067A7191997-10-10010 October 1997 LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed ML18067A6951997-09-24024 September 1997 LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts ML18067A5651997-06-0303 June 1997 LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested ML18067A5461997-05-12012 May 1997 LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities ML18067A4431997-03-24024 March 1997 LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS ML18067A4391997-03-21021 March 1997 LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired ML18067A4401997-03-21021 March 1997 LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr ML18066A8931997-02-21021 February 1997 LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr ML18066A8751997-02-0505 February 1997 LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr ML18066A8041996-12-23023 December 1996 LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment ML18066A7831996-12-16016 December 1996 LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced ML18065A9951996-10-0404 October 1996 LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg ML18065A9171996-09-0909 September 1996 LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr ML18065A8961996-08-29029 August 1996 LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments ML18065A8811996-08-20020 August 1996 LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced ML18065A8741996-08-16016 August 1996 LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected ML18065A8651996-08-12012 August 1996 LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr ML18065A8601996-08-0202 August 1996 LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit ML18065A8321996-08-0101 August 1996 LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board ML18065A7691996-06-12012 June 1996 LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr ML18065A6901996-05-0101 May 1996 LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr ML18065A6681996-04-22022 April 1996 LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr ML18065A5721996-03-11011 March 1996 LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded ML18065A5261996-03-0101 March 1996 LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr ML18065A5111996-02-19019 February 1996 LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr ML18065A5061996-02-19019 February 1996 LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts ML18065A5021996-02-15015 February 1996 LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr ML18065A4581996-01-31031 January 1996 LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr ML18065A4421996-01-19019 January 1996 LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr ML18065A4041996-01-15015 January 1996 LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr ML18065A3291995-12-0404 December 1995 LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr ML18065A2361995-11-0202 November 1995 LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr ML18065A2051995-10-20020 October 1995 LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised ML18065A0841995-09-18018 September 1995 LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr ML18065A0681995-09-14014 September 1995 LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line ML18065A0651995-09-0808 September 1995 LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment ML18064A8781995-08-28028 August 1995 LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage ML18064A8831995-08-21021 August 1995 LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr 1999-09-02
[Table view] Category:RO)
MONTHYEARML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18065B1151997-12-0909 December 1997 LER 97-013-00:on 971110,failure to Closure Test Two Check Valves Resulted in Violation of TS 6.5.7 Occurred.Caused by Close Function for Check Valves.Check Valves Tested to Confirm Proper Closure Capability ML18067A7751997-11-11011 November 1997 LER 97-011-00:on 971012,primary Coolant Pump Was Started W/Sg Temperatures Greater than Cold Leg Temperature.Caused by Inadequate Procedures & Operator Decision Making.Critique of Event Conducted W/Operators Involved ML18067A7581997-10-30030 October 1997 LER 97-010-00:on 970930,determined That Inadequacy in App R Analysis Resulted in Condition Outside Design Basis of Plant.Caused by Missing Cable in Circuit & Raceway Schedule. Developed New Evaluation Re ASD Valves Validation ML18067A7461997-10-23023 October 1997 LER 97-009-00:on 970923,discovered Procedure Weakness Re Implementation of App R Shutdown Methodology.Caused by Human Error.Revised Off-Normal Procedure ONP-25.2, Alternate Safe Shutdown Procedure. ML18067A7191997-10-10010 October 1997 LER 97-008-00:on 970912,spurious Valve Operation Could Result in Loss of Shutdown Capabilities Per 10CFR50,App R, Section Iii.L,Was Discovered.Caused by Failure to Validate Info from App R.Design Bases for SW Backup Reviewed ML18067A6951997-09-24024 September 1997 LER 97-007-00:on 970826,discovered Inadequate Testing of DG Sequencer Control Relay Contacts.Caused by Oversight on Part of Personnel Involved in Installation of Facility Change FC-800.Tested 106D-1/XL & 106D-2/XL Relay Contacts ML18067A5651997-06-0303 June 1997 LER 96-013-01:on 961115,DC Breaker Failed During Testing for as-found Trip Setting.Failure Caused by Oversight within Preventive Maint Program.Breaker Was Replaced & Tested ML18067A5461997-05-12012 May 1997 LER 97-006-00:on 970412,overtime Limits Were Exceeded for Radiation Protection Technicians.Caused by Inadequate Design,Review & Proper Verifications of Overtime Work Schedule.Communicate Overtime Limitation Responsibilities ML18067A4431997-03-24024 March 1997 LER 97-004-00:on 970221,trip of High Pressure Safety Injection Pump Occurred While Filling Safety Injection Tank Resulting in TS Violation.Caused by Particle Lodged Between Surface of Indication disk.Y-phase Relay Was OOS ML18067A4391997-03-21021 March 1997 LER 97-005-00:on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired ML18067A4401997-03-21021 March 1997 LER 97-003-00:on 961101,four Piping Lines Were Determined to Be Potentially Susceptible to Pressurization Due to Containment Temperature Increase During an Accident.Cac Discharge Piping Will Be verified.W/970321 Ltr ML18066A8931997-02-21021 February 1997 LER 97-002-00:on 970123,failure to Meet TSs 4.5.2d(1)(b) for Testing of Emergency Escape Airlock Occurred.Caused by Missed Surveillance.Emergency Escape Air Lock Testing Was Completed & Declared operable.W/970221 Ltr ML18066A8751997-02-0505 February 1997 LER 97-001-00:on 970106,TAVE Temp Dropped Below Minimum Temp for Criticality.Caused by Control Rod Withdrawal Rate to Increase Power Not Sufficient to Match Increase in Steam. Turbine Bypass Valve Actuator repaired.W/970205 Ltr ML18066A8041996-12-23023 December 1996 LER 96-014-00:on 961124,class 1E Raychem Cable Splices Were Installed Incorrectly.Caused by Incorrectly Made Electrical Splices.Total of 270 Splices Have Been Replaced within Containment ML18066A7831996-12-16016 December 1996 LER 96-013-00:on 961115,DC Breaker Failure During Testing for as-found Trip Setting Occurred.Cause Under Investigation.All molded-case Circuit Breakers in DC Distribution Panels Were Replaced ML18065A9951996-10-0404 October 1996 LER 96-002-01:on 960116,initiated TS Required Shutdown Due to Safeguards Cable Fault.Both Sets (Six Cables) of Cables Were Replaced & Installed Through Turbine Generator Bldg ML18065A9171996-09-0909 September 1996 LER 95-012-00:on 960809,TS Violation Occurred,Due to No Senior Reactor Operator in Cr.Caused by Extensive Remodeling.Cr Remodeling completed.W/960909 Ltr ML18065A8961996-08-29029 August 1996 LER 96-011-00:on 960730,CR Continuous Air Monitor Alarm Setpoint Improperly Established.Caused by Failure to Utilize Mod Process in 1988 Leading to Failure to Properly Select & Calibrate Instruments ML18065A8811996-08-20020 August 1996 LER 96-005-01:on 960207,determined Fuse on Main Supply to Two Safety Related DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Lack of Thorough Associated Circuits Analysis.Supply Fuse to Panels Replaced ML18065A8741996-08-16016 August 1996 LER 96-010-00:on 960717,high Pressure Safety Injection Pump Tripped While Filling Safety Injection Tank.Caused by Faulty 150/151Y-207 Time Overcurrent Relay.All Similar Relays in Time Overcurrent Application Have Been Inspected ML18065A8651996-08-12012 August 1996 LER 96-009-00:on 960712,identified Penetration Seal Deficiency on Fire Barriers Caused by Failure to Perform & Document Comprehensive Fire Barrier Evaluation.Developed Basis document.W/960812 Ltr ML18065A8601996-08-0202 August 1996 LER 96-006-01 on 960207,discovered Limits of Design Analysis Could Have Been Violated.Subsequent Tests & Analyses Facility Did Not Exceed Basis.Operating Procedures Have Been Revised to Treat 2530 Megawatts Limit as Absolute Limit ML18065A8321996-08-0101 August 1996 LER 96-003-01:on 960115,alternate Shutdown Panel Inverter Resulted in Unavailability of Panel.Replaced Defective Inverter Alarm Logic Board ML18065A7691996-06-12012 June 1996 LER 96-008-00:on 960513,fire Door Not Maintained Open in Accordance W/Design Basis.Cause Under Investigation. Engineering Evaluation Performed & Revised Documents, Surveillance & Test procedures.W/960612 Ltr ML18065A6901996-05-0101 May 1996 LER 95-001-01:on 950302,malfunction of Left Channel DBA Sequencer Resulted in Inadvertent Actuation of Left Channel Safeguards Equipment.Replaced microprocessor.W/960501 Ltr ML18065A6681996-04-22022 April 1996 LER 96-007-00:on 960321,inadequate Emergency Lighting & Ventilation in post-fire Safe Shutdown Areas.Caused by App R Program Documentation Insufficient to Demonstrate Regulatory Compliance.Lighting modified.W/960422 Ltr ML18065A5721996-03-11011 March 1996 LER 96-006-00:on 960207,average Reactor Power Level Exceeded License Limit Due to Insufficient Procedural Guidance. GOP-12 Revised to Treat 2,530 Mwt Limit as Absolute Limit Requiring Immediate Corrective Action If Exceeded ML18065A5261996-03-0101 March 1996 LER 96-005-00:on 960202,fuse on Main Supply to Two SR DC Panels & Panel Branch Circuit Breakers Not Properly Coordinated.Caused by Inadequate Electrical/App R Design Review.Implemented Hourly Fire tours.W/960301 Ltr ML18065A5111996-02-19019 February 1996 LER 94-012-02:on 940427,determined That Internal Ground in Thermal Margin Monitor Causes Nonconformance W/Rps Design Basis.Incorporated RPS Failure Modes & Effects Analysis in Plant DBD.W/960219 Ltr ML18065A5061996-02-19019 February 1996 LER 96-004-00:on 960118,SIS Disabled W/Primary Coolant Sys Greater than 300 F.Caused by Personnel Error.Permanent Maint Procedure to Disable/Enable SIS Actuation on Low Pressurizer Pressure Will Be Revised to Align W/Ts ML18065A5021996-02-15015 February 1996 LER 96-003-00:on 960115,technicians Found Low Voltage cut- Off for Alternate Shutdown Panel Inverter Set That Resulted in Unavailability of Panel.Caused by Inadequate Post Mod. Readjusted Set Point to Minimum setting.W/960215 Ltr ML18065A4581996-01-31031 January 1996 LER 96-001-00:on 960103,failed to Test Duplicate Equipment. Caused by STS No Longer Containing Requirement for cross- Train Testing of Duplicate Components.Will Submit Request to Delete Subj Requirements from TS.W/960131 Ltr ML18065A4421996-01-19019 January 1996 LER 95-016-00:on 951226,did Not Analyze Primary Coolant Samples within 72 H.Caused by Belief Acceptability to Save Pcs Samples for Choride Analysis Past 72 H.Counseled Chemistry Supervision.W/960119 Ltr ML18065A4041996-01-15015 January 1996 LER 95-014-00:on 950119,PCP Oil Collection Deficiencies Created by FC-860 Piping Mod.Caused by Inadequate DBD for Sys & Lack of Review by Experienced Fire Protection Personnel.Updated Design Basis documentation.W/960115 Ltr ML18065A3291995-12-0404 December 1995 LER 95-013-00:on 951103,circuit Fuse Coordination Deficiency Which Affects App R Safe Shutdown Equipment Noted.Design of Fuse Coordination in Potential Transformer Circuits Will Be Evaluated & Modified as required.W/951204 Ltr ML18065A2361995-11-0202 November 1995 LER 95-012-00:on 950701,discovered Unqualified Electrical Connection in Containment SW Outlet Valve Controller.Caused by Failure of Assigned Engineers to Available Info.Replaced Wire Nuts W/Inline Butt connections.W/951102 Ltr ML18065A2051995-10-20020 October 1995 LER 95-008-01:on 950728,discovered That None of Four Containment High Pressure Channels Would Initiate Reactor Trip Due to Programmatic Deficiencies.Administrative Procedure (AP) 9.44,AP 9.45 & AP 10.44 Will Be Revised ML18065A0841995-09-18018 September 1995 LER 95-011-00:on 950817,CR 40 Withdrawal Occurred When Given Insertion Signal Due to skill-based Error in Crimping & Removing Foreign Matl from CRDM Motor Connection Box.Crd Package replaced.W/950918 Ltr ML18065A0681995-09-14014 September 1995 LER 95-010-00:on 950815,ESFA Resulted in Manual Rt Following Isolation of Pcs.Replaced Failed Instrument Line ML18065A0651995-09-0808 September 1995 LER 95-009-00:on 950728,discovered Lack of Procedural Guidance for Pump Repair Following Fire.Proposed Use of Power Supply Breaker Did Not Adequately Address Effect of Loss of Control Power.Performed Independent Assessment ML18064A8781995-08-28028 August 1995 LER 95-008-00:on 950728,discovered During Design Change Testing That None of Four Containment High Pressure Channels Would Initiate Rt.Caused by Programmatic Deficiencies. Reviewed Selected Tests & Mods from Recent Refueling Outage ML18064A8831995-08-21021 August 1995 LER 95-007-00:on 950720,discovered That 12 Instrument Loops Had V-bolted Type Qualified Cable Splices Connected to Wires W/Exposed Kapton Insulation.Caused by Human Error.All V- Bolted Splices Replaced w/in-line design.W/950821 Ltr 1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested 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 ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30
[Table view] |
Text
consumers
.Power * .. - G.B Slade Gmeral Manager POWERINli
.MICHlliAN"S PROliRESS
' *Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert, .Ml 49043 March* 6, 1992 Nuclear Regulatory Commission Document Control Desk
f;"*: .*
- ~ . DOCKET 50-255 .- LICENSE.DPR-20 PALISADES PLANT .
- LICENSEE EVENT REPORT 92-004-01-LOSS OF CONTAINMENT INTEGRITY DUE TO THE FAILURE OF THE EMERGENCY. ESCAPE AIRLOCK EQUALIZING VALVE - SUPPLEMENTAL REPORT Licensee Eve~t Report (LER)92-004, Supplement 1 i~ attached. Thi~ suppl~ment quantifies the amount of radioactivity released to the environment as a. result of this event, includes a discussion of the safety significanc~ of the event
_and clarifies that maintenance, and not replacement, will be performed on the inner door equalizing valve. This event was originally reported to the NRC in accordance with 10CFR50.73(a)(2)(i)(B) as a condition prohibited by the plant's technical ~pecifications.
h/L--rk~
- Gerald B Slade General Manager r:- .
CC Administrator, Region III, USNRC NRC Resident In~pector - Palisades.
Attachment
,- r *~ .. r* , .
~. ......= -~ .:~.
9203110119 920306 PDR ADOCK 05000255 S PDR . A CMS ENERGY COMPANY
llllC--
le-831 LICENSEE EVENT REPORT (LEA)
U.I. lllUCLUll 111011\.ATOllY Ca
..-OVID OM1 lllO. lt1D-01CM
- ION PACILITY lllAMI 111 IDOCl(IT . . . . . . . Ill I ~- llll
_ p,,i;~~r1.,., Pl<>nt- 0I&101.0101215 15 1 !oF 01*
TITLI "' LOSS OF CONTAINMENT INTEGRITY DUE TO* THE FAILURE OF THE EMERGENCY ESCAPE AIRLOCK F()TTAT T"Tl\l~ VAT.VF IYINT DA Ill Liii 11..-111 111 lllPOlllT DA I
- OTMlll PAclLITI YID Ill R .PACJLITY NAMU OOCltlT llUMSllllCll NI A O I I0 I0 I0 I I I
~ 1 011 9 912-010~ -011 013 *~6912 N/A 0 I I 0 I 0 IO I I I II llll'OllT II SU.ITTIO PUllllUANT TO THI lllQUllllMINTI : --.If I Ol'llUTlllO *.
lllQDI Ill l'Olllllll ID.!llDC" ao.*c.1111111 I0.4111Ccl ao.ac.1111 -- ID.71411Qlllwl ID.71411Qll*I n.11~1 n.111.i L~;-;,~L 1 10 I ID.4111Clll1llMI ID.4111C11111111H
--x 111.ac.1121 I0.71!.1121111 -- 111.nc.11211.. 1 ID.711111QllwlllllAI OTMlll 16-"Y In~
- - - "' Tur. NltC ~-
atsAJ 1*.*:*'.***.:.:*:-: .. ;.:*:*::*:*:*:*;*;*;
- ltjAME t*:*'*'.**'.***:*:-:-:*:*:**;-:-:*:.*:*::*:*:.*:*;
ID.4111Clll1Hlwl IO.*Clll1 llwl
~
"°.71!.lllllUI I0.71ClllllllUI LICINllE CONT II .I
- 121 111.nc.1a1111111ia1 ID.7Jl81Qllal TILll'HOllll NUMllR
- . AllllA COOi Cris T Hillman, Staff Licensing Engineer COW'LITI ONI LINI POii IACH COWONINT PAILUlll OllClllllO IN TMll llll'OlllT C111 CAUSE SYITIM COMl'OJjENT x N 1H I I 1L W I 310 12
- Yes :,:,-:.; .;.;.;.: ........ :*:*:*>: :*:-*:-: I I I I I I I
I I .I I I. I I ...;.;.: :-:*:-: .......... *:*::::::::::::::: I .1 I I I I I
"'"'LIMINTAL llll'OAT IXl'ICTIO IHI Xl YU (If ..... - IJCl'IC'TID IV*Mt$SION DATii h NO lllPICTIO IUIM1$SION DATE 11&1 01 5 oi 1 91 2 AUTllACT (I.Im/I ID 1400 -
- I.*.. _,.,.;,,..,.,, fl'-it 11¥*-IP<<* ry-'nwn /ina/ 1111 On January 7, 1992, at 0435 hours, with .the pl ant operat i hg at 100% power,, it
~as determined that containment integrity, as defined in_Technical .
Specifications 1.4 and 3.6.la, had been violated. At. the time of discovery the* plant staff was perfo~ming technical .specifications surveillance procedure
{TSSP) S0-4b, "Escape Air Lock Penetration Leak Test." The escape air lock was last satisfactorily tested on July 10, 1991; This event is not considered a safety significant issue since a significant radiological source term did not exist* when containment integrity was violated on January 6, 1992. Therefore, the impact on the health and safety of the public was insignificant. This is further supported* by the fact that the outer door of the escape air lock was operable and only one door of an air lock is required for coritainment integrity.
The proximate cause of this event was that the escape air lock inner dtior equalizing valve was stuck in the open position, thereby defeating the isolation capabilfty of th~ inner door. No root cause for the valve sticking open has been determined at this time. I Corrective action for this event includes revising the maintenance procedure for the. airlocks to require that the equalizing valves be visually checked following the completion of the s~al contact check, performing maintenance on the escape air lock.inner door equali~ing valve during the 1992 Refueling I
Outage and quantifying the amount of radioactivity released as a result of this event.
'°""-
'..JI "'-'C~l&a *IQIJ\,..ATQa-. :C11M11QH)ll LJCENSEE EVENT REPORT ILERI TEXT CONTINUATION
.r.-0~10 owe* ..o 1°~'°"
11**11(1 l/l1 '5
- tiell.ITY 11AM1 Ill OOCUT lllUllll* 121 llQ1JllOT14~ -**IOIO llllflJMa** .......
Palisades Plant TIXT ,, _ _ e .__---lac,.._.-.*" 1111 01 5 EVENT DESCRIPTlON On* January 7, I992, at 0435 hours; with the plant operating at IOO% power, it was determined that containment [NH] integrity, as defined in Technical .. -
Specifications 1.4 and 3.6.Ia, had been violated. At the time of discovery the plant staff was performing technical specifications surveillance procedure (TSSP) S0-4b, "Escape Afr Lock Penetration Leak Test."* The escape air lrick
[NH;AL] was last tested on July IO, I99I and was found to be satisfactory with a leak rate of 102.8 cc/min.
One of the early procedure sieps in JSSP S0-4b is to perform a visual insp~ction uf the sealing ~urfaces of both the inner and outer escipe air lock*
doors. On January 6, I992, an auxiliary operator entered the escape air lock*
to perform that inspection. *Nothing unusual concerning the operation of the* ..".,; .1 ....*
~scape air lock was noted. However, during the initial pressurizatiori of the escape air lock following the inspection, it was determined that the pressurization time was longer than what had been experienced.during previous.
tests. At 0329 hours, the Shift Supervisor decided.to calculate a leak rate at the pressure attained to. that time, approximately 45 psi a; which is less than containment design pressure of 69~7 psia. (Although IO CFR 50, Appendix J, requires that test pressures be greater than the design p~essure, TSSP so~
4b, step 5.3.I4, instructs .the operators to continue the test at the
- obtainable pressure.)_ Temperature and ~ressure data ~as taken for one minute and a leak rate of approximately I,000,000 cc/mi~ was calculated. The leak rate obtained was assumed to be representative of the actual leak rate which was in .excess of the allowable leak rate of 65,200 cc/min, as defined in Technical Specification 4.5:2-. Soap bubble testing was performed on all
- escape air lock fittings outside containment. Additionally, th~ outer door viewing port, outer door seal area and the outer door equalizing valve were all thecked for leakage and none was friund. These tests-confirmed that the outer door of the escape air lock was not the source of leakage. The outer door of the escap~ air lock was locked closed and the inner door was declared inoperable. Personnel entered the containment via the personnel air lock to
. inspect the inner door of the escape air lock. Upon inspection, the escape air lock [NH;AL] inner door equalizing valve. [RV] was .found to be stuck open.
The inner door equalizing valve was initially closed by pressing on the*valve mechanism which freed up the valve and allowed the return spring to close the valve. The valve was manually operated four mor~ tim~s and each time return spring action immediately closed the valve. Test data was obtained to verify escape air lock integritj and calculations were performed for a I-hour leakrate. The caltulated I-hour leak tate was within the acceptance criteria of TSSP S0-4b. Following the successful escape air lock test~ the valve was stroked 6 more* times without sticking. As a result of the successful test and the acceptable performance of the inner door equalizing valve, both the inner door and the outer door of the escape air lock were considered operable and containment integrity had been re-established. However, the inner door is being administratively controlled using the equipment protection tagging program (yellow caution tag). Use of the escape air lock ts restricted;
'JI '."UC::.lAA *IGL.rt. .. TO*., :a...11SJ()ll LICENSEE EVENT REPORT ILERI TEXT CONTINUATION **.-ov10 owe ..o* i, '°~'O..
*****u *n*"
OOCUT...,_111121 Pali.sades Plant 9 2 - 0 0. 4 - 0 1 0 3 OF 0 5 T'IXT ,,_...., * - - - - _ _ , _ ........111171 opening the inner. door may render the door inoperable *since operation of the door_may still cause the valve to stick in the open position.
This event was originally reported to the NRC in actordance with . I 10CFR50.73(a)(2)(i)(B) as condition prohibited by the plant's.technical specifications. * *
- . ~.:_
PROXIMATE CAUSE The escape air lock inner door equalizing valve was stuck in the open positiori, thereby defeating the isolation capability of the inne~ dopr.
ROOT CAUSE No root caose had b~en d~termined ~t this time.
This event *involved the failure of the containment escape air lock .. The escape air lock is designed to pre~ent a radiologital effluent release path to the ~nvironment and, therefore, is equipment that ii important to safety.
This event did not involve personnel error.
'ANALYSIS OF EVENT Palisades Technical Specific~tions, Section 1.4, Item a under Containment
.Integrity, requires that one door on each air lock (i.e., personnel and escape) be properly closed and sealed whenever containment integrity is required. Furthermore,. Technical Specification 3.6~la requires that containment integrity, as defined in Section 1.4, shall not be violated unless the reactor . is in the cold shutdown condition. Contrary to these requirements, on January 6, 1992, containment integrity was violated during the escape air lock seal inspection, which was being performed in conjunction with TSSP S0-4b. .
There are two possible occasions when the escape ai~ lock inner door equalizirig valve could have stuck open to cause this event. The valve could either have stuck open following the seal contact check performed as part of TSSP S0-4b on July 10, 1991 or following the seal .inspection performed as part of TSSP S0-4b on January 6, 1992. *However, we believe that the equalizing
.valve stuck open during the seal inspection _performed on January 6, 1992.
This position is supported by the fact that the operation of the escape air lock inner door equalizing valve was checked following the completion of S0-4b on July 10, 1991, at which time no problems with the inner door equalizing valve were ident1fied. -
..JI "-'C::..t.AA 8IQW1.ATO*.,* :~ 1 -.,()frl LICENSEE EVENT REPORT ILEA> TEXT CONTINUATION *-oveo oi.ie ..o 1* 9C...Q1o.e h***u *1.11 n
. **o* *JI
-*. *~ ***~*
Palisades Plant 0 4 OF 0. 5 A***review**of the:*act.tvities *which ..occurred *as**a *normal**part'of **theperformance of. TSSP S0-4b, :indicates that *in two separate instances on January -6,
- 1992,
- .. ,._.:containment**"i*ntegrtty,:.was Yi*olated~*:;::*:.TheseAnst:anc.es~are~descr.ibed ,-below..
. ,__ ** <On January .6 ;: .1992,.
- the,.A1,1xi l fary. Operator opened* the:*escap_e: air; *1 ock
~, .*'.. * * *"""l>t.iter .:"door*to*,*exit:*,*the*escape "air *lock *following -the*"'i*nspecti'on;**of the * * * .. *
... ; (\ . .L.'::d.nner,door .._ * , ... , . ****.***.... _,:;,.,;~.~~.;i:"';**.~ ......"" ...
.. *I{
** ~ **.
-~... * **
'*.* . - ~-
..... -.* .. ;*on **January
- 6, * ;1992;~ 'maintenance -men,' opened :the 'outer "door ~to =enter*. the ......J.
*. :c* *'.'esca,pe .:air:: 'lock* and""i Qstal l *:the *. .strong backs*' on<*the* *tnner *door.* * ."
. . '_; ~<. *..*.....';~ :.. :
. Once it' was:determined that the inner door equalizing valve was the source of .:~q ,
the leakage, the outer door was not-opened until*the inner door had passed the . *i
- --*leakage*"*test~ 'This *'test* was . conducted --on '*January '7 ;--:1992;~*and .. resulted in a ..._, __ '"" "~*"*~ *
.. -~-leak r-ate of., 87...4. "cc/min. *. * * .* * . . ** ::'-" _.,,,, .":, . ... )
.-:~
. *:.: *~' *. :.*... .~. ::~ ,.::.::.;..::. ..:.. ; - }
Safety Si.gnificance
.. .:. .The.' . l oss*.;of:::cont.ainmen.t :.tot~grJty~.:~on . ;,J.anuar.y -,~, ..::J9,9.~.:.res.1Jlted,jn *'.th,e. :creatjon :.'. , * :-.....
*. **,*..,.of '~an"*'unmon'ltored ' ratJi*ofo'g'i't<<fl *'c:re*1 *eas EfJ)ath"to *~the **'*enVlranmene;*=**:~*Th*er*iffore *; . *. an(:~" *. *-* * *: .
. assessment.:of.. the . _imp.acL.on ...the .hea lth . . and. safety...of..the .pub lic . . was .per.formed. 1. :..........i . :
.: To:**,adc;ine,.$.s*::*~the *_;:JS.:$iU.e~l. . .:t.i,j!!p:a~t*~~on:::t-:be ;~tubltc . ~:b.e_alt.h::~and. . .s.~'feJ:Y.;. -.;,the .....*,,:,....~ *"J *. -~*. * * '*.:t:* ..
. .r.adi.oJogi.caL . condit.i-_ons ;;of th.e :*pr.imary:,*cool!tnt -system, :*the :*second!tY:'Y r:(,steam ; '*""; '*:* :,,;u;,~ ,....
.. gene.rator}o:system and '.the :.containment atmos_phere, _prior to . and during 'the .. : .*. .f: ...
*:event,* were'rev'*iewed. **"'This was'.:-necessary since* a :1e*ak on=*:t*hEf'"A:*::'steam *i*;:: ':!/':._ * *
*... generator:;:secondary' .s-i de' :h*and *hole' ex i s.ted--~and *:some. *f uel ~as semb1'r*l ea ks*,:were-.J;;:~~ * :.- .. :
*--P~esent ....:r:;,Jhis .cr~.ated:. a .. potent.ial ..leak .path..from . the. l?.CS..into ..the .ste.am .... _,_.'.' "" >"**:
. generator Jhroygh ~a *~postulated. tube leak; out of the. steani gener,_a~or throµgh .* *"* .":*:*
th *tf:'teaktritj *'"lla nd':;;h"Ole ~"ill to ";:the*;*;to*nta tnme*nt ;_~::atmo:s'Jlher:e:;:~::::o t:if ;~*of :-cont*a:i nmettt' * .;. :.:1o-* :L .* .;~ * *,. *
. through the-:escape* *air *-lock inner door .equalizing :v_aive* .and'<:fi.nally'.to'*;the***:,:'..; , .. * *
**en*v*1**ronment*
. - . * *. . . . th*r.ough***the*vop*en-.:.ou-teri"..door*
-:**~* ... . . ~.. '#.'. . *~ .* :'.
1
-:~* :of... ' ...the *-es-c*ape,;'. "'l**r *-1 ock ** ... , * * .,,. '::;-i:t;;**;:::!i
-~- .*.;..;;a~ ...., . . ~~-- ~-*: ...-.,.:.:** ... :.:*:**,* *-: *.......... , '"' *.* *.:,'-,.". '
*~**.
. . . . . .. . .. . .. . . . ~ . ... .. **.
. . .... . . . ~ * . . .. - . *. ..: .,,; >::.-"!.**.* *.. '. ! '* '-; *.- >:...:*'.:-=-:: :;:: ,: _;_.;-;.::, ...-*X -,
PCS' gamrna*~a-Cl,*lfty' ;fdf**the*:**week'-~prior:to'.. the*~event ;* . lricludi n'g *'the.-dayjof".the *. ~- *: ":* ... ::* *
- ev'ent ;~'.-sho~d -no. unusual or~sign'ffitant -increases.** **.sross. gamma. analy§fs' 'of. ; -.::;.. ':)j:ffi:
th*e_.~_wat.er..-:::j:n.~.:t.he:~:.~s.~:c.ond.ary>:.s.i-de~.o"f~:;.t~*e .. -,si~~m~::g.eraef.a*to.~.s:.=~fr-~.m~=:.J.~.o.~:ary.~.&.;:**~::l.992. .~-~****
and: Januar.Y. 7, 1992* ~howed*le*ss :than~detectable acti:YHY~ *The ,ra9iolqgital * :'..
conditions* of the containment wete.also reviewed~* He*alth *physics:Togbook *data* *
- for *i'odi n*e~"'~:parffculate:'*and"TIObte*"gas :*a*cti~vtt*i es *for . ~a *containmen:t"* a*i r sample "
taken A n'.*.c-0njunctj. on,:.wJth,_._a-.-,conta-tnment~,,_entr:y .. made;,.,On.:December .31, .*l99J. ~we~e . -=-- *** ......
..::'~compa,red.~-:t~o *!h~ . .~a,i.r:- . ,-sampl~; . ,result:s-,taken.~dur,;.ng ,.the ..,-con;tainment .. entry,,-on ;- ... "
. January 7~~.::1992 . . - .....
. ::No .
.s.ignifi.cant .di.fterences.
in ~activity_.were
~ .. . . ,, .'
~~~~.t:!d
**.A:~ca*l .cu"l,atton:*~w:a:s~-:p*er.:formed: ".-to:~-iquant'ify .:th.e*c.<amo.unf,:o'f. *:.acti\1 i ty *" releai.ed: to:*ih*e:*.'; **
env i.r.onment "as _.. a . r..eslil.t. of . ,:th is.:...event .....Jh..is ..calculat i.on .. ~is _,documented .,i.n.~an.
*.engineer,ing ,.analys;i~s :.(.EA.-..£::.:PAL-:,;92,';"00lE'."..01:) ... ~ ....J:he . ::calcul.atJori showed,..thaLa .* .
- total of 1~35E-2 curies of.activity wa~ r~leas~d. This ~onstitutes 3.27E~3%
*-of the. total--*maximum permissible concentration*(MPC); as defined in our
1111*c *., ... .-..
<MJI * .JI .. ..,C~lAa llG1.J1..£TO*., :011M1G'Otll LICENSEE E ENT REPORT ILEA) TEXT CONTINUATION *-Ovto owe .,iJ i*'°~'~
h**lll(S liJI 11 OOCUT ~Ill 111 **
~*11-~11111 Palisad~$ Plant*
05000 255 2 - 0 0 4 - 0 1 0 5 OF 0 5 TIXT ,, _ _ * , _ . - _ _ , _ iw.. m.*11117!
Off-site Dose Calculation Manual {ODCM); using the most ~onservative site boundary dose dispersion factor.
This release will be included in the next Semi-Annual Radioacti~e fffluent and
*Waste Disposal Release Report as required by Palisades Technical Specification_
6.9.3.1.A .and.10CFR50.36a.
Therefore, since a significant radiological source term did not* exist when containment integrity was violated on January 6, 1992, and the release through*
the escape airlock was small., the impact on the health and safety of the public was insignificant.
Furthermore~ since the outer door of the escape air lock was determined to be oper~ble and bnly one door*of an air lock is required for containment integrity, according to the technical specifications, there is no safety
. significant issue regarding this event.
CORRECTIVE ACTION
- i. The maintenance proced~re for the airlocks will be revised to require that the equalizing valves be visually checked following the completion of the seal contact ch~ck.
2; A work order was written tci pe~form maintenance on the equalizing valve during the 1992 Refueling Outage.
- 3. *Perform a calculation to quantify the amount of radioactivity released. '
i..
to the environment as a result of this activity. Incl~de thi~
information in the annual radiological effluent release report ..
- ADDITIONAL INFORMATION A second supplement to this LER will be submitted after the 1992 refueling
- outage.}}