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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] |
Text
- *.l
- G B Slade . - _
General Manager POWERING MICHIGAN'S PROGRESS Palisades Nuclear Plant: 27780 Blue Siar Memorial Highway, Covert. Ml 49043 Febr~ary 1~, 1992
. Nuclear. Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 LICENSE DPR-20 .PALISADES PLANT .
LICENSEE EVENT REPORT 91-014, SUPPLEMENT 1 - SAFETY RELATED CIRCUITS .
. ROUTED WITH OPPOSITE CHANNEL CIRCUITS* . .
Licensee Event Report (LER) 91-014-1 is at~ached. Thi~ ~upplemental. ,.
repbrt provides additional irrformation not ~ontained in the original submittal. These changes are indicated by a vertical Hne in the right
- hand margin. This event is reportable to the NRC per *
- 10CFR50.. 73(a)(2)(iiJ, as a condition outside the design bas.is.
~~
Ger~ld B Slade
- General Ma_nager CC Administrator, Region.Ill, USNRC
- NRC Resident Insp~ctor - Pal.isades Attachment 9202210364 920214 PDR ADOCK 05000255 S PDR '
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- 1.1.. -....-~ - . , . . _ . , _ _ , _ 11- 1111 Through the on-going Palisades 'configuration Control identified. Project a number of routing have been Previous apparent discrepancies in circuit 1991 provided NRC correspondence dated September 4, 1990 and March 12, details of the 11 Circuit and Raceway Schedule Enhancement Project" and status of the projeCts activities. The *electrical circuit .channelization and . separation deficiencies which have.been evaluated *at thi.s time, while not conforming ta ~SAR criteria in a11 *respects, have resultt;!d in i dent ifi ca ti on of very few conditions i nvo.l vi ng a loss of electrical or protection system independence; or noncompliance with 10 CFR 50, Appendix R requirements.
- In those few*cases, two to date, compensatory measures in plant Technical and corrective actions have been taken as stipulated Specifications and/or the condition was pr9mptly corrected. At the timeto of the event the plant was operating at about 70%.power and escalating is reportable as a ..
foll power fo 11 owing a *Short outage. This event
- Condition outside the design basis of the pl ant.
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LICENSEE EVENT REPORT ILERl TEXT CONTINUATION **,*c:ac*.!*: : ... e . . c ~*~-.;*~
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'4CILITY ...... 111
...... *AOI :JI Palisades Pla;-i:
0 5 0 0 0 2 5 5 9 1 """'"'. Q 1 4 .:_ 0 1 0 2 OF 0 T'l)CT ,,, - - * ~- - , , _ . . "'!C """" ....,, 1171 tvent uescr1pt1on .
The Palisades Co~figu~ation Ccintrol Project (CCP) whic~ was irtitiated in 1987 included an effort to verify and correct plant electrical drawings, including the plant circuit and raceway schedule.* This effort involved development of a circuit and raceway schedule data b~se, as well as verification of selected portions of circuit routin~~. Throtigh this effort a n_umber of apparent discrepancies in circuit* routing have been identified. This event invol~~s approximatelj 40 circuits which were believed to be safety-related circuits routed with opposite channel*
circuits. Previous pla~t deviation~reports involving apparently misrouted circuits includ~ O-PAL-89-147, D~PAL-90-4Q, D-PAL-90-221, arid O-PAL-90~222. *All *of the apparently misrouted circuits from these earlier-deviation r~ports that have been evaluated, have been I*
dispositioned as either not being safety-related and therefore .
channelized circuit routing is not an issue, or* the circuit misrouting is.
not a safety concern because the failure of the circuit does not le~d to -*
. unde~irable consequences (i.e. the circuit fail~ safe). Additional_
background and information on the CCP circuit and raceway enhancement .
project was provided to the NRC in our letter dated_ September 4~ 1990 .. A.
status update on the project was provided in our letter dated March. 12, *
.1991.
At the ti me of the event 'the p1ant was opera.ting at about 70% POY'er and esca1ating to full power following a. sh~r~outage~
. :~ .
The _physical_ separation a*nd channelization. deficiencies.thatAha*ie been identified appear to ~esult from two sepa~ate failures: . 1) K non~uniform interpretation of design criteria for channelizing and rquting electrical circuits, and. 2) the unavailability:of a single, ~omplete and reliabl~
source of design doc~mentation for electr~cal *circuit routing and chan~elization. ..
- Ana.lys is of the Event Cable Separation Design Criteria The design criteria which were originally used at Palisades to provide physical independence between redundant 'electrical circuits were submitted to the Atomic Energy Commission (AEC) on May 28, 1969; This submittal contained, in pa~t, our re~ponse to a request for information regarding the triteria and associated bases used at Palisades duri-ng initial design arid installat1on of electrical circu.its. The guidelines that are currently used dur1ng design of electrical cables and raceways are essentially unchanged from those of the original design period and
.. I .. 1...c:.:.A.1111 *E*~ ...... ; : q .. :.:.. .... a *.: ...
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- ACILITY llolAMI 111 Liii llol~lll *ti **a* .:ti Palisades Plant 0 5 0 0 0 2 5 5 9 1 - 0 l 4 - 0 l 0 3 OF 0 5
- TtXTiw--*are*remct~~n~~li.'tcseC:tion 8.5.3.l. FSAR Section 8.5.3.1 states that circuits belonging to safety-related power distribution channels~ reactor protection system ~hannels, engineered safeguards channels or other safety-related system channels will be run in sep~rate raceway systems, and that "physical separation, (distance}, is considered to be most reliable method of providing.circuit separation and isolation."
In practice, the design criteria for physical separation and independ~nce of electrical circuits are primarily satisfied by r6uting electrical cables in channelized cable raceways, and by maintaining a separation diitance between these channelized raceways~ This method of providing.
physical separation between redundant el~ctrical circuits meets the intent of curreritly acc~pted standards and guidelines and has been reviewed and determined to be acceptable.* Palisades was designed prior t6 issuance of Regulatory Guide 1.75, "Physical Independence of
- Electrical Systeins," the AEC General *Design Criteria for physical.
independence of electrical circuits, or the associated IEEE standards
. (IEEE 279, IEEE 384).
Circuit Separation and Channelization Anomalies_ .
We have identified several examples where the channelization ~f installed
- electrical cables does not satisfy our original design criteria. The
~ctual n~mber of electrical cable separation and channelization
. discrepancie.s identified so far represents only a very small percentage . "
(les~ than one percent) of the o~er thirteen thousand el~ctrical cables .
that we have ev,aluated. As. a' result of these cable routing anomalies, we
. have undertaken a programmatic effort to identify and resolve those physical separation and channeliz~tion discrepancies that may exist, and we have taken steps to prevent promulgation of similar discrepancies in the. future.. We have al so. taken actions to address the physical
- separation and channelizatidn deficiencies Which have been identified to date.
- The ele~trical circuit. channelizati~n and separati~n deficiencies which
. have been evaluated at this time, while not conforming.to FSAR criteria in.all respetts, have resulted in identification of very few safety-significant conditions involving a loss bf:electrical or protectibn system .independence or noncompliance with 10 CfR 50, Appendix R
. requirements. In those few cases, two to date, compensatory measures and*
corrective actions hav~ been taken.as stipul~ted in plant Technical Specifications _and/or the condition was promptly corrected.
Pa 1i sades has taken an aggressive position in ifs response to the tdentified electrical cable routing and channelization discrepancies through the. Electrical Cable and Raceway Separation Issue Resol_ution Plan. Thi~ plan addresses the causal fact6rs for these coriditions and proposes actions to prevent reoccurrence. The key ptovisions of this plan include: 1) publication of clear procedural guidance relative to cable routing design criteria, 2) availability of reliable circuit design information, 3) field review of installed raceways, and 4) evalu~tion and
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- LJCENSEE EVENT REPORT (LERl TEXT CONTINUATION *P* 0 c.. e: :~I .. c :*~.....;*:,..
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0 5 0 0 0 2 5'591 ..:...01 4 - 0 l 0 4 OF 0 5 T'IXT.'*--r~l1't.1"m'l~"iam;it'i1t'ied cable* routing and channelization discrepancies.
- As we.have.done in the past, we will - _ _ .
evaluate confirmed cable routing and separation discrepancies for safety-significance and 9perability impact when they are identifi~d, and
_compensator~ and corrective measures wi 11 be pursued, as necessary.
This event is being reported under -10CFR50.73{a)(2){ii) as a condition outside the design basis of the plant. _ -
Corrective Action -
Corrective actions addressing circuit channelization and separation deficiericies began.with the Electrical .Cable and Raceway Separation Issue Resolution Plan. A summary and *implementation schedule for these actions was pr6vided in our September 4, 1990, *"Submittal of Additional information Related to th~ Circtiit and Raceway Schedule Enhancement Project," and a status update was provided in our March 12, 1991 letter.
The actions and their current status are listed below: -*
- l. The design and licensing basis for channelization and physical
- separation of electrical circuits h~s been reconstituted and
. consolidated in a siri9le document, the "Electrical Separation Design Criteria and* Licensing Basis." -
- 2. Guidance has been developed in Administrative Pr-ocedure 9.35; "Circuit and Raceway Schedul~," for control and ent~y of design information in. the Cable and Raceway ..Schedule . .
(CRS) database. -
~
- 3. Cable routing ~eq~irements and ~ractices have been incotporated.
into Engineering Guidelines: EM-22-04, "Channel Separation -
Cable Routing Instructions;" EM-22-03, "Fir:e Protection - Cable Route Verification;" EM-22-06, "Cable Routing - EEQ Requirements;" 1-EGAD-PROJ-08, "Cable Sizing Guid!:!l ine - Ampacity;" and EGAD-'-PROJ-.
03, "Electrical Engineering Separation Criteria, Practices and Exceptio.ns." * *
- 4. A physical review of installed cabl~ raceways has been performed
- in order to identify installations that do not meet design
s.* Design information relative to the channelization and physical
. routing of electrical circuits and raceways will be enhanced.
This action wil} include validation and completion of information contained in. the CRS database and is c~rrently*expected to be
- complete prior to September 30, 1992.
6.* Electrital cable separation arid channelization anomalies identified during our review of physical raceway installation~
will be evaluated and appropriately d:ispositioned. The schedule
- for resol~tion of these items is dependent on the number and type of items identifi~d during the review.
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LICENSEE EVENT REPORT !LERl TEXT CONTINUATION .t.P*ac*~e: : ... 1 -.c :*;..;~*.:...
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. For the sp~cific circuits fo this LER, the Configuration Control Proje.ct (CCP)*Electrical Cable and Raceway Separation Issue Resolution Plan is intended to address the root cause of this event and no furthei
~orrective actions to prevent recur~ence are proposed at this time.
- Remedial actions for the.recently identified specific circuit routings are as follows: * . .* . * . .*
A.* Since only class 1E circuits require physical separation of channelized circuits, the safety classification of each potentially misrouted circuit will be reviewed.
B. The in~plant routing of each potentially misrouted safety-related channelized circuit will be verifi~d. * * *
- c; A fu~thet irivesti~a{ion of th~ original plant design basis for .
physical separation of safety-related circuits w~s completed .
. . Based on the results of this review,* tbe EGAD-PROJ-03, "Electrical Eng~neering Separatiori Ciiteria, Practices, and exceptions," was *
.revised. .
I D. Each confirmed circuit channeliiation defici~ncy ~ill be evaluated with regards to equipment operability and l_OCFR50. 59. Appropriate compensatory measures and. corrective actions as ~ti pul ated in
- plant Technical Specifications will also be taken. A list of
- confirmed circuit channelization deficiencies is prov.ided in the
. attachment to this LER; * *
- Ph~si~al separation of improperly ch~nnelized, safety-related
- circuits will. be established on a schedule consistent with the safety significance of the deviation.
If it is determined t_hat failure of the improperly channelized, safety-reJ~ted circuit . does not adversely affect accomplishment of a safety function, the circuit may be left as currently routed.
Such conditions will be clearly documented in the circuit and
.raceway schedule ..
F. *Confidence.in the accuracy of the circuit routing data in the Circuit .and Raceway Schedule was evaluated, and it was determined that additional .verification *inspections are.not needed to assure that circuit. channelization deficiencies have been identified.
Additional Information*
None
Attachment LER 91-014 CONFIRMED CIRCUIT CHANNELIZATION AND SEPARATION DEFICIENCIES Scheme. Scheme Name Ntn>er of Operable UnrevieWed Carment '
Circuits Safety Question B293 Diesel Generator Room Cool i ng 2 No No When the condition was* discovered a temporary Fan V24C .- modification was performed to remove reliance on' V24C.
- This c.ircuit has been. re-routed to provide:
proper physical separation ..
S65 Reactor Protection System 1 Yes No Failure of circuit does n'ot adversely affect accomplfshment-of the safety function.
IP 73 Pressurizer Narrow Range 1. No Yes When the condition was discovered a temporary Pressure modification was performed to disconnect the circuit. Proper physical separation wi 11 be
. . established .
SOB Servjce Water System Valves 1 Yes No Failure of this circuit does not adversely affect accomplishment of the safety function.
G06R. Diesel 1-2 Auxiliary Skid 1 No No Failure of this circuit. does not adversely ~ffect accomplishment of the safety function in short term
( 2-*4 hours). Long term operator actions are addressed in plant procedures . .Proper physical seoarat ion wi 11 be established.
S16 Component Cooling Water Valves 1 Yes No Failure of .this circuit does not*adversely affec(
accomplishment of the safety function.
D408 Control Room HVAC Emergency 1 Yes No Failure* of this *circuit does not adversely affect Actuation accomplishment of.the safety function; however*,
0
- position in~ication for ventilatiOn system dampers.
may be lost. This Regulatory Guide ~.97, Category 2 instrumentation is not required to .meet the single failure criterion .
521 and Waste System Containment 19 Yes No Failure of these clrcuits does not adversely affect S22 Isolation Valves accomplishment of the Safety function; . however, containment isolation valve position indication niay Miscellaneous Containment be lost. This Regulatory Guide 1.97, Category 1 S25 and Isolation Valves 17 Yes No instrumentat iOn is required .to meet the .single.
S26 failure .criterion. The instrumentation* was not upgraded with regards to physical separation when Regulatory Guide 1. 97 was
- imposed by NRC Generic Letter 82-33 .. This was due to our failure to recogniz_e that 'phys ica 1 separation criteria .were not met. This condition is being evaluated to :
-. determine if the circuits*should be reverified to provide proper physical separation, or if justtfication exists to request NRC apprrival of a deviation from the Regulatory Gulpe 1.97 requirements.