Forwards LER 97-011-01 Re Starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps.Commitment,Listed
Person / Time
ML18068A481
Site:	Palisades
Issue date:	10/29/1998
From:	Thomas J. Palmisano CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18068A483	List: 05000255/LER-1997-011, :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 05000255/LER-1997-011-01, Forwards LER 97-011-01 Re Starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps.Commitment,Listed
References
NUDOCS 9811090129
Download: ML18068A481 (1)
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LER-1997-011, Forwards LER 97-011-01 Re Starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps.Commitment,Listed

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2551997011R01 - NRC Website
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l l A C~"Energy Company October 29, 1998 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, ~ 20555 Palisades Nuclear Prant 27780 Blue Star MemotiaJ Highway Covert, Ml 49043

.. DOCKET 50-255 - LICENSE DPR PALISADES PLANT Tel: 616 764 2296 Fax: 616 764 2425 LICENSEE EVENT REPORT 97-011 STARTING OF PRIMARY COOLANT PUMP

. __ c... _WITH _STEAM GENERATOR TEMPERATURES GREATER THAN COLD LEG.

'"'..,,;;,;<~:~TEMPERATURES. *.

i: t~~~*~~~~~~~1i1!:.~~~~~;~~';,

,:- **.. :.. ~.::10,GF~ 50.73(a)(2)(i)(B), as a Condition prohibited by the planrs Technical.

., * *~-..~) S~cations. *The cover letter transmitting.th8.LER stated that the informati9".l

. -. ~;*::~,*.. :;~-

. ****~-- provided was "prellminai'y in "natl.ire; arid that the *results of the Completed revieW would be provided in a supplement to the LER. The enclosed supplemental LER reflects the

.results of this review and the corrective action taken to improve the applicable procedures.

SUMMARY OF COMMITMENTS This letter contains no new commitments and no revisions to existing commitments.

One commitment is being closed with this letter. That commitment was:

... -**Strategies for primary coolant pump starting will be reviewed and the procedure will be revised to incorporate clearer guidance fqr steam generator conditions and temperature measurements.

~y~

Thomas J. Palmisano Site Vice President CC Administrator, Region Ill, USNRC Project Manager, NRR, USNRC NRC Resident Inspector-Palisades Attachment 98110.90129 981029-;-

PDR ADOCK 05000255 S

PDR

.....,-~

Licensee Event Report

Palisades

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		Reporting criterion
05000255/LER-1997-001-01, :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	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	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000255/LER-1997-002-01, :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	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	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000255/LER-1997-003-01, :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	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	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000255/LER-1997-004, :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	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	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)
05000255/LER-1997-005, :on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired	on 961220,operation of Plant Outside Design Basis Occurred Due to an Unacceptable Repair on Main Steam Isolation Valves.Pipe Plugs Permanently Repaired	10 CFR 50.73(a)(2)
05000255/LER-1997-006, :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	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	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000255/LER-1997-007, :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	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	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000255/LER-1997-008, :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	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	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)
05000255/LER-1997-009, :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	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	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)
05000255/LER-1997-010, :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	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	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)
05000255/LER-1997-011-01, Forwards LER 97-011-01 Re Starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps.Commitment,Listed	Forwards LER 97-011-01 Re Starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps.Commitment,Listed	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000255/LER-1997-011, :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	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
05000255/LER-1997-012, :on 971017,deenergized Control Rods While in Power Operation.Caused by Failure of Individual Barriers to Prevent Inadequate Performance.Post Maint Testing Was Performed.Pages 5,6 & 7 of Incoming Submittal Not Included	on 971017,deenergized Control Rods While in Power Operation.Caused by Failure of Individual Barriers to Prevent Inadequate Performance.Post Maint Testing Was Performed.Pages 5,6 & 7 of Incoming Submittal Not Included
05000255/LER-1997-013, :on 971110,determined Check Valves in Min Flow Recirculation Piping from Discharge of Each HPSI Pump Were Not Periodically Tested to Confirm Closure Capability.Caused by Inadequate Understanding.Database Revised	on 971110,determined Check Valves in Min Flow Recirculation Piping from Discharge of Each HPSI Pump Were Not Periodically Tested to Confirm Closure Capability.Caused by Inadequate Understanding.Database Revised	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)

05000255/LER-1997-011-01, Forwards LER 97-011-01 Re Starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps.Commitment,Listed

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