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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] |
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{{#Wiki_filter:consumers
* /)..S.8 Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 July 3, 1980 1YIT J &'!le s G Keppler Office of Ir:.spectior. and Enforcement
}\egion I I I U S Nuclear :Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 6013'(
DOCKET 5~-255 - LICENSt: :C.PR-~20 -
P.i\I,IS*.A.DES ?L..4.NT - UP~..~TE OF LICEJ:JSEE
]~'i.EI,TT RE~PORT 80-01 7 I.iicensee Eirent Report (LEI\) 30--0lT was submitted. to the ~:EC, ?.egion III ofr':'...ce CJn ~Jur1e 13, l9b0. C!l the ye*verse side is an upda.te o~ I..icen:=ee f~-ve!it Feport 80-017. Changes are indicated b;-f a vertical line in the righ-'.:. har:.d ma::-gin.
Rog~~!' \{ Hustor~
Senior Licensing ~ngineer CC fiirector, Office of Nuclear Reactor Regulation Director, Office of Inspection ar:.d EEforcement IIBC :5:.esident Inspector - Pali sad*.=s r.IUL 7
?0070 /0319 1980
(
LTPDATE REPORT - PREVIOUS REPORT DATE - June 13, 1980 PALISADES PL.ANT NRC FORM366 U.S. NUCLEAR REGULATORY COMMISSION*
(7-77)
LICENSEE EVENT REPORT CONTROL BLOCK: i-1_..__.__..__.__.__-,!IQ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
~IMI IIPIAILlllG)lolol.-lulololol Ol-lo!OIG)l4111111111©L I I 7 8 9 LICENSEE CODE 14 ~5 LICENSE NUMBER 25 26 LICENSE TYPE* JO 57 CAT 5B CON'T CITTI ~:~~; U;J© I o I 5 I u I o I 01 Cl I 5 I 5 101 o ! 5 11 Io I 8 I o I@ I o 17
' a 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
~eview of PS testing procedures revealed the setpoint of PS-1801 thru 1804
~ ~o be lower than permitted by TS 3.16. PS-ldOl-1804 sense containment IT:EJ !pressure and are used to initiate RPS tri us (one switch contact) and SIS/
C2:II) pant. isol/cont gpray (other contact). The procedure (RI-04) required
[]]]] §etting both switches to operate at less than 5 psig \RPS setpoint I.AW l1JIJ ~S 2.3); whereas ESFAS required setpoint per TS 3.16 is 5.0 to 5.75 psig.
III]] ICondH.-ipp did. not preyent EffF' systems f'rom f'imctionjn~ properlv. __J 7 8 9 SC SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE suacoo~ COMPONENT CODE SUB CODE SUBCOCE
[ill] Is IHI@ IJLl@ I z I@ LI IN Is IT IR I u1e L§J@ L~@.
7 8 9 10 11 12 13 18 19 2C SEQUENTIAL OCCURRENCE REPORT REVISION
(';:;\ LE RiRO CV ENT YEAR REPORT NO. CODE TYPE NO.
\;.:.J REPORT !8 I0 I l.=J 101117 I 1......-1 I 013 I W l=.l Ll-.J NUMBER ~I 22 23 24 26 2i. 28 29 30 J1 32 AC710N FUTURE EFFECT SHUTDOWN (.;';;\ ATTACHMENT NPRD~ 'PRIME C:OMP. COMPONENT TAKEN ACTION ON PLANT METHOD
- HOURS ~ SUBMITTED FOAM SUB, SUPPLIER MANUFACTURER W@lzJ@) W@ W I o Io I o I 01 L!J@ L..!J(§ ~@ 1u p 17 !5 i@
33 34 35 36 37 40 41 42 43 44 .,
CAUSE OESCRIPTION AND CORRECTIVE ACTIONS @
LOri.,:inal procedure author apparently did not recognize different setpoint
[JJJJ req'iirements of TS 2. 3 and 3 .16. Procedure has been revised such that bot4
!IITI 'T'S ? *3 and 3 .16 are satisfied. \Each switch can be independently set).
[i]JJ Reuortable under TS 6.9.2.B.1.
lJJil 7 8 9 80 FACILITY STATUS % POWER OTHER STATUS tJOI
\::::,/
METHOD OF DISCOVERY DISCOVERY DESCRIPTION @
f1EJ IG ! 1010 101@IN ...... A
. . _ _ _ _ __. ~@ NA 7 8 9 10 12 13 44 45 46 so ACTIVITY CONTENT ~
RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @
~ I z I @ Li@ I....._r-r_.A_ _ _ _ _ ____. I..___ NA 7 8 9 10 11 44 45 so PERSONNE~ EXPOSURi':S Q..
NUMBER A TYPE DESCRIPTION
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NUMBER DESCRIPTION~
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Genlinsl Offlc.n: 212 West Mlchlg11n Avenue, Jeckson, Michigan 4Sl201 * (517) 788-0650 July l, 19/jQ Mr James G Keppler Office of Inspection and Enforcement Region III U S Ni..;,clear Regulatory Commission 799 Roosevelt Road Glen Elly:i., IL 60137 DOCKET 50-255 - LICENSE DPR PALIS.AI::ES PU.JfT - LICENSEE EVENT RE~ORT 80-019 - SIRW T.4.HK LEVEL On the reverse sid.e is Licensee Event Renert 80-019 't1hi*~h is re-;:orta-::;le tue.der Technical Specification 6.9.2.A.8.
- Ca:;id. ? Hoffman Nuclear :Uicensing Ad...'!i.inistrator CG Director, Cffice of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement
- NRC Resident Inspector - Palisades f.JUL 3 1980
"I'.~"
; ,,
PALISAJJES PLANT NRC FORM366 . U.S. N.UCLEAR REGULATORY COMMISSION f7*771 LICENSEE EVENT REPORT CONTROL BLOCK:* !-1_*.;..*.._1_...._....._.:._-1..---il0 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
[ili] IM I
- 7 8 9 I I pI LICENSEE CODE Al L I 1 101 14 ~5 0 I 0 I- I0 I 0 I 0 I 0 t..ICENSE NUMBER I 0 I- I0 I 0 101 4 11 I 11 1 11 101 25 26 LICENSE TY~E JO I
57 CAT !;II I 0 CON'T
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~G~~~ UJ©I 01 s I oI 01 oI 21 s Is K2)1 o I 6 Io 1*9 I 81 o IG)I 01 T I o1.i I 8 I o 10 60 61 OOCICET NUMBER 68 69 EllENT CATE 7' 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@ .
ID11rjpg review of basis for T.S. 3 3 jt was deternjped that the SIRW tank
[]JI] 1should contain enough borated water to provide 250,000 gal of injection
[§JI] ld11r;pg safety ;pjectfop. '1'.S. 3.3 reqpjr<=>s tenk total cqprents rq be
[Ill] 1250,000 gal; consequently when RAS occurs, less than 250,000 gal would be
[]]]] !injected. This condition adversely affects post acc1dent containment lr:l;'1
~ 1press.ure ana ..., ysis. I Reportability determination made on. 6-16-80.
cmJ8 9 80 SYSTEM CAUSE CAUSE COMP, VALVE CODE cooE SUSCOOE COMPONENT CODE SUS CODE suscooE.
[ill]
7 8 Is 9
!Bl@ 10 w@ w@ I z I z I z I z I z1z1e w@ w@
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@ LER'RO CVENTYEAR REPORT NO. CODE. TYPE NO.
REPORT .
NUMBER I8I0I
- 1l :;*
I ! I aI J I 21 1.....-1 I a I , 29I . L1:J 1=J l.Q.J
- O:J 24 26 Z7 ZS Jo J1 J2 Ac:'!ON FUTUF>E EF=-ecT *SMUTOOWN f.:'.::\ ATTACMMENT Nl'RD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METMOD MOURS SU8MITTEO FORM SUB. SUPPLlcR MANUFACTUR~R W@W@.
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[J]]J I Wo-rdinll of T.:'. 1 1 1a was not snffjcient1y prerise Cnrrentlv. tank
):'*
IIJil I volume is being administratively controlled to maintain 250,000 gal above D:lJJ RAS setpojnt. SIRW tank Jqw ]<=>yel aJara setpqjpt wiJl be chang<=>cl r_o o::m reflect new limit. Need for T.S. Change will be further evaluated.
CTI!]
.7 a 9 so FAC:L..1~ ~ METMCC OF P.\
STATUS °'POWER *. OTMER ST... TUS \.::;:! DISCOVERY DISCOVERY DESCRIPTION ~
[ill] W@ I 01 g I s lL-1 La..J~~'--=T~*~S~.'--'B~a~s~i=*~s~R~e~v~i~e~w;_,___________.....
1 a 9 ACTIVITY
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45 co 80 RELEASED OF RELEASE . "'MvUNT OF ACTIVITY LOCAT10N OF RELEASE @':
~
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[!JI]
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12 13 , *.*
- ac --J PERSONNEL INJURIES Co\
NUMBER OESCRIPTION6 mJa I9 0 .I 0 I 011I@) ~12~----,;;,;;,;...,
NA ______________________________ ---:--e~c LOSS O< OR CAMAGE TO FACILITY r.;J'\
- TYPE DESCRIPTION '\:.:::,J.
C2TIJa W@ ~10~---~---o.i.a."---------------------------------~s~o 9
PUBLICITY C\ NRC USE ONLY ISSUED(:".:;\ DESCR1irr10N ~
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a 9 ~10--------~-~-------------------~sa N!\ I I I I I I I I 6~9..;,,,..i....;._._,.;,,.,,_._._. . . . . _. .I_,aoI
' ~-,
General Offices: 212 West Michigan Avenue, Jackson, Mlchl911n 49201 * (517) 788-0650 Ju~y l, l.9ti0 Mr .James G Keppler Office of Inspection and Enforcement Region III U S Nuclear Regulatory CoI1JII1ission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - L~CENSE DPR PALISJ-\~ES ?LftJfT - LICENSEE EVENT REPORT 80-019 - SIRW T.AJ:IK LEV'EL On the reYerse sid.e is Licensee Event Report 80-019 'N"hich is reportable 1m.d.er Technical Specification 6.9.2.A.8.
Da*;id. ? Hoffman Nuclear Licensing A;ln;j nistrator ...
*:1 CC Director, Office of Nuclear Reactor Regulation Director, Office o:., Inspection and Enforcement Tu"RC Resident Inspector - Palisades FJUL 3 1980
NRC FOJ'!M~
- PALISADES PLANT U.S. NUCLEAR REGULATORY, COMMISSION
'7*771 LICENSEE EVENT REPORT CONTROL BLOCK: I~,~--.......~----~---~61...:..1 I(,"\ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lTiiJs 7
IM I I I p I Al L I i 101 oI o1- Io I o I o I o I o I - I o I o 101 4 I 1 I 111 11 101 I I0 9 LICENSEE CODE 14 ~5 1*.ICENSE NUMBER 25 :26 LICENSE TYPE 30 57 CAT !OB CON'T
~~~~~ L.!JG)I 01 5 I o I 01 o I 21 5 I 5 GI o I 6 Io I 9 I 8 I o IG)I 01 T I o 1.L I 8 I o 10
- 0JJa 7 60 61 DOCKET NUMBER 68 69 EVENT DATE 7* 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES @
[ill] !Durjng rey;ew of basjs for T.S. 3 3 H was determined that the STRW tapk
[]JI] 1should contain enough borated water to provide 250,000 gal of injection CIT!J ldtir;ng safety ;n-iection. TS. 3.3 ri:><.jufres tank total eontent"' ro he
[§JI] 1250,000 gal; consequently when RAS occurs, less than 250,000 gal would be
[]JI] !injected. This condition adversely affects post accident containment
[TII) 1pressure analysis. Reportability determination made on 6-16-80.
cmJ 7 8 9 BO SYSTEM CAUSE CAUSE COMP. VAL.VE cooe cooe SUBCOOE COMPONENT CODE suacooE SU BC ODE
!IIIJ 7 B ls I Bl@ w@ w@ 1z1z1z1z1z1z1e 9 10 ,.. ,~ l:l 16 w w@
lS 20 SEQUENTIAL OCCURRENCE REPORT REVISION
- 0. LEi<'RO CVENTYEAR REPORT NO. COOE TYPE NO.
\:..:.,; REPORT I 8 I0I
~:l,....._...,.._~_
lol1191 I/I lol1I L1:J l=J l.QJ NUMBER.
2 24 2e: 27 28 :t9 . JO 31 32
.o.cr:oN FUTUPE EFFECT SHUTDOWN A ATTACHMENT NPRQ-4 PRIME COMP. COMPONENT TAKEN ACTION ON PL.ANT METHOO HOURS \:31 SUBMITTED FORM ~UB. SUPPLIER MANUFACTU~E~
l£J@W@
3J J*
W@
35 W
36 I oI 31 OI o I o I lllJ@>
40 41 lliJ@
42 W
43 I Z! 9 l 9 I 9 I@)
.... 47 CAUSE DESCRIPTION ANO CORRec*nve ACTIONS @
[[[[] I Wo..-dinji qf T.S. 1 3 la was DO'" s11fffrjently precjc::e. C1p*re:itl v tank ITJJJ volume is being administratively controlled to maintain 250,000 gal above RAS setpojnt. SIRW tapk Jaw l<=>y<>l alarm 5i:>tpoint wi11 be cbff'"'f;Pd t"Q reflect new limit. Need for T.S. Change will be further evaluat:ed.
c:ma 9 80 FACIL1~ . rjQ\ METHOD OF (.;:;\
STATUS % POWER OTHER STATUS '.::;:/ OISCOVERY OISCOVERY OESCRIPTION 'CJ UiiJ W@ I ol 9 I sl@L.____...N....,A_ _ _--' LAJ~~I~-~~~~*~S~*....;B~a~s~i~s=--R~e~v~i~e~w:....~~~~~~~-'
a s 10 n 13 45 46 80 ACTIVITY RELEASED OF RELEASE CONTENT AMOUNT OF .O.CTIVITY e
(.;;;\
LOCATION OF REL.EASE @)
G:TIJa 1
W@ lz.J@ ...
g 10 I ___t....M.___ _ __...
11 45 80 PERSONNEL. EXPOSURES Q-,
NUMBEP. (.;':;\TYPE DESCRIPTION 82] I o I o I ol~W@>._I--'N=A;;;,___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___.
1 a s 11 12 13 so
. PERSONNEL. INJURIES ~
NUMBER DESCR1PT10N'!2J Lill I 0 I 0 I OI@
8 9 11 NA
~,2~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~8~0 LOSS O* OR 0.0.MAGE TO FACILITY t.;31 n'PE DESCRIPTION '.::.:;J
!2TIJ 8 9W@ ~10~~~~~~~~........__~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~BJO PUBLICITY C\ NRC USE ONLY ISSUED(;".;\ DESCRll"T10N ~
[ill]a IJij1~~------N:.:.A:.!------------------J s 10 68 I I 59 II I 11 II I I ao I}}