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| {{#Wiki_filter:""'* | | {{#Wiki_filter:""'* |
| .,I | | .,I GB Slade General Manager POWERING MICHIGAN'S PROGRESS Palisades Nuciear Plant: 277e0. Blue Star Memorial Highwa~. Covert, Ml 49043 . |
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| * GB Slade General Manager POWERING MICHIGAN'S PROGRESS Palisades Nuciear Plant: 277e0. Blue Star Memorial Highwa~. Covert, Ml 49043 .
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| January 6, 1994 J | | January 6, 1994 J |
| Nucl.ear *Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - | | Nucl.ear *Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - |
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| Gz::~,£,* | | Gz::~,£,* |
| General Manage~ - .. | | General Manage~ - .. |
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| | CC Administrator, Region III, USN.RC NRC Resident Inspector - Palisades Attachment 9401140099 940106 r* |
| CC Administrator, Region III, USN.RC NRC Resident Inspector - Palisades | |
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| Attachment 9401140099 940106 r* | |
| PDR ADOCK 05000;)55 ' | | PDR ADOCK 05000;)55 ' |
| S PDR r | | S PDR r |
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| EVENT DATE 161 LER N.UMBER 181 . REP.ORT DATE 1111 OTHER FACILITIES INVOLVED 181 | | EVENT DATE 161 LER N.UMBER 181 . REP.ORT DATE 1111 OTHER FACILITIES INVOLVED 181 |
| >: SEQUENT!~ REVISION FACILITY NAMES MONTH DAY YEAR YEAR NUMBER I<. NUMBER MONTH DAY YEAR N/A o I 6 I o I o I I I o | | >: SEQUENT!~ REVISION FACILITY NAMES MONTH DAY YEAR YEAR NUMBER I<. NUMBER MONTH DAY YEAR N/A o I 6 I o I o I I I o |
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| i I 2 0*1 7 9 3 913 oI ll 4 01 o 01 1 01 6 9 I. 4 N/A 0 1 1°1°1°1 I 6 | | i I 2 0*1 7 9 3 913 oI ll 4 01 o 01 1 01 6 9 I. 4 N/A 0 1 1°1°1°1 I 6 |
| THIS REPORT*IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: IC/Wck..,,. Ol""'°'9of11N following) 1111 | | THIS REPORT*IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: IC/Wck..,,. Ol""'°'9of11N following) 1111 OPERATING N |
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| | I 20.4021bl 20.4061cl 60. 7 31all2Jlivl 73.711bl MODE 181 POWER' LEVEL 1101 do Io - 20.4061*111 Jlil 20.4061*111 Jliil - |
| OPERATING N | | 60.3111cll11 60.3111cll21 60.731all2JM 60.731*112Jlviil 73.711cJ OTHER (Specify in A119u.., |
| I 20.4021bl 20.4061cl 60. 7 31all2Jlivl 73.711bl MODE 181 | |
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| POWER' LEVEL 1101 do Io - 20.4061*111 Jlil 20.4061*111 Jliil - | |
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| 60.3111cll11 60.3111cll21 | |
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| 60.731all2JM 60.731*112Jlviil | |
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| 73.711cJ OTHER (Specify in A119u.., | |
| </. | | </. |
| -- -L 20.4061all1JliiiJ 60.73(*11211il 60.731all2JlviiiJIAI below - In Tex!, | | -- -L 20.4061all1JliiiJ 60.73(*11211il 60.731all2JlviiiJIAI below - In Tex!, |
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| .\ >* . *. | | .\ >* . *. |
| 20.4061*111 Jlivl 60.731*11211iil 60.731*112JlviiiJIBJ NRC Form 388AJ | | 20.4061*111 Jlivl 60.731*11211iil 60.731*112JlviiiJIBJ NRC Form 388AJ |
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| OPERABILITY DETERMINATION | | OPERABILITY DETERMINATION |
| * The electrical penetrations ~re considered operable because the function of the penetrations as a barrier to containment leakage is maintained; however, the level of redundancy, in terms of the number of electrical penetration barriers, may be reduced under certain scenarios (e.g., earthquakei and tornados} due to the design deficiency. | | * The electrical penetrations ~re considered operable because the function of the penetrations as a barrier to containment leakage is maintained; however, the level of redundancy, in terms of the number of electrical penetration barriers, may be reduced under certain scenarios (e.g., earthquakei and tornados} due to the design deficiency. |
| The reduction in the level of redundancy is acceptable on an interim basis because: (1) the integrity of innermost barrier is maint~ined under all scenarios; (2) the barriers are periodically tested per lOCFRSO, Appendix J, to prove their functionality as a containment leakage barrier and; (3) the electrical penetrations have been operated and | | The reduction in the level of redundancy is acceptable on an interim basis because: (1) the integrity of innermost barrier is maint~ined under all scenarios; (2) the barriers are periodically tested per 10CFRSO, Appendix J, to prove their functionality as a containment leakage barrier and; (3) the electrical penetrations have been operated and |
| ~aintained in accordance with the manufacturer's requirements (i:e., with the space between the barriers filled with nitrogen). | | ~aintained in accordance with the manufacturer's requirements (i:e., with the space between the barriers filled with nitrogen). |
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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
""'*
.,I GB Slade General Manager POWERING MICHIGAN'S PROGRESS Palisades Nuciear Plant: 277e0. Blue Star Memorial Highwa~. Covert, Ml 49043 .
January 6, 1994 J
Nucl.ear *Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
LICENSEE EVENT REPORT 93-014 - FAILURE OF ELECTRICAL CONTAINMENT PENETRATIONS TO. MEET DESIGN FEATURES DESCRIBED :IN TECHNICAL SPECIFICATIONS AND FSAR Litensee Event Report (LER)93-014 is attached. This event is reportable in accordarice with 10CFR50.73(a)(2)(ii)(B) as a condition outside the design basis of the plant.
Gz::~,£,*
General Manage~ - ..
CC Administrator, Region III, USN.RC NRC Resident Inspector - Palisades Attachment 9401140099 940106 r*
PDR ADOCK 05000;)55 '
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- .. A CM5 ENERGY COMPANY
NRC Fonn 3118 U.S. NUCLEAR REGUlATORY COMMISSION 111:831 APPROVED OMB NO. 3160-0104 EXPIRES: B/31 /86 LICENSEE EVENT REPORT (LERI FAC:UTY NAME 111 DOCKET NUMBER 121 PAGE 131 Palisades Plant 015101010121515 . 1 I 0 14 OF TinEPAILURE OF ELECTRICAL CONTAINMENT PENETRATIONS TO MEET DESIGN FEATURES DESCRIBED IN
'l'Ff'J.lNT<~AT C::PFf'T14'Tf'A'l'H1NC:: ANn l<'C::AR -
EVENT DATE 161 LER N.UMBER 181 . REP.ORT DATE 1111 OTHER FACILITIES INVOLVED 181
>: SEQUENT!~ REVISION FACILITY NAMES MONTH DAY YEAR YEAR NUMBER I<. NUMBER MONTH DAY YEAR N/A o I 6 I o I o I I I o
i I 2 0*1 7 9 3 913 oI ll 4 01 o 01 1 01 6 9 I. 4 N/A 0 1 1°1°1°1 I 6
THIS REPORT*IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: IC/Wck..,,. Ol""'°'9of11N following) 1111 OPERATING N
I 20.4021bl 20.4061cl 60. 7 31all2Jlivl 73.711bl MODE 181 POWER' LEVEL 1101 do Io - 20.4061*111 Jlil 20.4061*111 Jliil -
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20.4061*111 Jlivl 60.731*11211iil 60.731*112JlviiiJIBJ NRC Form 388AJ
- * * ) **\ < * // ; \ 20.4061a111 JM 60.73(*112Jliiil 60.731all2Jlxl LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER Cris T. Hillman, Staff Licensing Engineer COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 sARIEA1cl°Es I 7 I I 4 I -I aI s I I 3 s
1 CAUSE SYSTEM COMPONENT MANUFAC*
TUR ER REPORTABLE TO NPROS /)'( CAUSE SYSTEM COMPONENT MANUFAC*
TUR ER REPORTABLE TO NPRDS I I I I I I *1 I !ti'. I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 I* I. I I I I. I I MONTH DAY YEAR EXPECTED n YES Vf yH, compi.r. EXPECTED SIJBMISSION llA TEI ~NO SUBMISSION DATE 1161 I I I ABSTRACT UJmit to 1400 .,,..... i:e .. _.,,,m.re1y fiftfffl llingle--* typewritten line*I 1181 O~ Dece~ber 7, 1993, at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br />, with the plant operating at 100% power, ft was determined that the containment electrital penetrations in the north and southwest penetration rooms did not meet all the desi~n criteria specified in the Palisades Final Safety Analysis Report (FSAR) and the Techn1cal Specifications. In each room, a non-seismic nitrogen system is connected to each electrical penetration between the double barriers. Furthermore, the bottles and connecting pigin~ for the nitrogen system to the southwest penetration room _lie outside the auxiliary ui ding and, therefore, are not tornado protetted. .
- The cause of this event w~s inadequate design contiol. The design of the electrical.
penetrations was modified in 1970 and again in 1982 without recogniiing all of the design requirements of the electrical penetrations as contai~ment isolation boundaries.
Corrective action fot this event includes evaluating avpropriate actions to address the deficiencies in the electrical.penetration design, eva uating the co~tainment isolation boundaries for the electrical penetrations, incorporating electrical v*enetration design require~ents f9r the nitrogen suepJ{ into plaryt desi~n docu~eryts, imp ementiryg,permanent corrective action for the electrica penetration desifin deficiency, and providing a lessons learned memo to ~lant engineers emphasizing t e evaluation of functional interfaces when making c anges to plant equipment.
- ./ NRC Form-3HA U.S. NUCLEAR REGULATORY COMMISSION 19-831 APPROVED OMB NO. 31~104 EXPIRES: 8/31186 LICENSEE EVENT REPORT ILERI TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER !21 LER NUMBER !31 PAGE !41 SEQUENTIAL REVISION
. YEAR NUMBER NUMBER PALISADES PLANT 0 I6 I0 I0 I0 I2 I6 I6 9 I3 - 0*1 1 I 4 - 0 I0 0 12. OF 0 I4 EVENT OESCRIPTiON
- On 0,ecember 7; 1993, at 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br />, with the pl ant* operating at 100% power, it was determined that the containment electrical penetrations [NH;PEN] in the north and southwest penetration room~ did.not meet all the design criteria specified in the Palisades Final Safety Analysis Report (FSAR). The deficiency was identified during design engineering of a modification t~ the nitrogen supply for the north penetration room.
Technical Specification 5.2.2a states that all penetrations through the steel-lined concrete structure for electrical conductors, pipe, ducts, air locks, and.doors are of the double-barrier design. FSAR Section 5.8.6.2.2 also desc~ibes the electrical containme~t penett~tions as being of a double barrier design. In additiori, FSAR Section
.5.8.6.2 states that all containment penetrations are seismic and tornado protected. The penetrations in the north and southwest penetration rooms do not meet all of these requirements in that, in each room, a non-seismic nitrogen system is connected to each electrical penetration between the double barriers. Furthermore, the nitrogen bottles arid connecting piping for the nitrogen system to 'the southwest penetration room lie outside the auxiliary building and, therefore, are not tornado protected .
. This event is reportable to the NRC in.accordance with*IOCFR50.73(a)(2)(ii)(B) as *a condition outside the design basis of the plant. I CAUSE OF THE EVENT The cause of this event *was inadequate design control. The design of the electrical penetrations was modified in 1970 without recognizing all of the design requirements of the electrical penetrations as containment isolation boundaries. The design was further modified in 1982 without recognizing the design requirements of the penetrations.
ANALYSIS OF THE EVENT The design specification for the electrical penetrations (E-20) required a double barrier design with a 1/4-inch test port o.n the exterior side of the containment. The original intent was to install a threaded plug in the electrical penetration which could be removed to allow for leak rate testing.
- The design was modified in 1970, prior tQ initial plant operation, to provide a bottled nitrogen supply, pressure gauges, a tubing -network, and fill connections to each electrical penetration for the purpose of pressurizing the space between the double barriers with nitrogen as a m~ans of controlling corrosion. The 1970 modification was apparently performed without consideration of seismic requirements. No record of this modification exists, other than a letter directing its installation. In 1982, the nitrogen bottles for the southwest penetration rdom were relocated to the turbine building to resolve a personnel safety concern during bottle repl~cement. The 1982 modification did not consider the tornado protection r~quirements for the system when the nitrogen bottles were relo~ated.
NRC F0tm 3HA U.S. NUCLEAR REGULATORY COMMISSION lf-831 APPllOVU> OMB NO. 31~104 EXPIRES: "8/31186 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION
.., FACILITY NAME l1l . DOCKET NUMBER 12) LER NUMBER 131 PAGE 141 SEQUENTIAL REVISION YEAR NUMBER NUMBER PALISADES PLANT 0 5 0 0 0 2 5 59 3 - 0 1 4 Q 0 Q 3 . OF Q 4 CORRECTIVE ACTION The evaluation of cor,rective actions is ongoing and involves researching regulatory and industry design requirements for electrical penetrations, plant specific licensing commitments, design requirements specified by the penetration manufacturer, designs of similar electrical penetrations at other nuclear power plants, and contact with vendors of similar electrical penetrations. This research is complicated by the fact that the vendor of the Palisades el~ctrital pen~trati6ns (Viking) is no longer in business. Our initial assess~ent of the electrical penetratidn design requirements indicated that the nitrogen supply is important to maintaining the integrity of the electrical penetrations by reducing the potential for humidity induced corrosion of electrical conducting surfaces and contacts. Therefore, our preliminary conclusion is that the nitrogen supply should not be isolated.
The followin~ correcti~e actions have been .. developed to address this event:
- 1. Evaluate appropriate remedial corrective actions.to address the deficiencies in the electrical penetration design. *
- 2. Evaluate the ISi containment bounda~ies for the electrical penetr~tions in light of this design discrepancy. Revise containment isolation boundary tagging and containment leak rate testing prdcedures, as appropriate, based on this
- 3. Issue updates to P&IOs, add valve numbers, "Q" list interpretations, and the Equipment Data Base for the north electrical penetration nitrogen purge system.
- 4. Evaluate the necessity of having a nitrogen purge continuously in the electrical
~enetr~tion. The evaluation should include the effects for inter~al corro~ion occurring after deletion of the riitrogen purge .
. 5. Provide a lessons learned memo to plant engineers emphasizing the evaluation of functional interfaces wh~n making changes to plant equipment.
OPERABILITY DETERMINATION
- The electrical penetrations ~re considered operable because the function of the penetrations as a barrier to containment leakage is maintained; however, the level of redundancy, in terms of the number of electrical penetration barriers, may be reduced under certain scenarios (e.g., earthquakei and tornados} due to the design deficiency.
The reduction in the level of redundancy is acceptable on an interim basis because: (1) the integrity of innermost barrier is maint~ined under all scenarios; (2) the barriers are periodically tested per 10CFRSO, Appendix J, to prove their functionality as a containment leakage barrier and; (3) the electrical penetrations have been operated and
~aintained in accordance with the manufacturer's requirements (i:e., with the space between the barriers filled with nitrogen).
cl NRC .Foim 3HA U.S. NUCLEAR REGULATORY COMMISSION
'- lf-831 APPROVED OMB NO. 31~104 EXPIRES: 8131186 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION FACILITY NAME 11'1 DOCKET NUMBER 121 lER NUMBER 131 PAGE 141 SEQUENTIAL REVISION YEAR NUMBER NUMBER PALISADES PLANT 0500025593_Q14_ 00 Q 4 OF Q 4 The operability requirements for the containment electrical penetration barriers are contained in Section 4.~ of the plant Technical Specifications. Section 4.5, "Containment Tests," addresses the requirements for local leakage te~t. The electrital penetration barriers have been shown to meet the acceptance c~iteria in this section.
Therefore, inter~m operation with the electrical penetration design .deficiency is authorized by the plant license.
ADDITIONAL INFORMATIO~
None