05000364/LER-1998-001, Forwards LER 98-001-00 Re Manual Reactor Trip Due to Dropped Control Rod K-2.Two NRC Commitments Contained in Corrective Action Section of LER

From kanterella

(Redirected from 05000364/LER-1998-001)

Jump to navigation Jump to search

Forwards LER 98-001-00 Re Manual Reactor Trip Due to Dropped Control Rod K-2.Two NRC Commitments Contained in Corrective Action Section of LER
Person / Time
ML20217A247
Site:	Farley
Issue date:	04/16/1998
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217A250	List: 05000364/LER-1998-001, Forwards LER 98-001-00 Re Manual Reactor Trip Due to Dropped Control Rod K-2.Two NRC Commitments Contained in Corrective Action Section of LER 05000364/LER-1998-001-05, :on 980328,manual Reactor Trip Due to Dropped Control Rod K-2,was Determined.Caused by Overcurrent Condition.Crdm Cable & Connectors Associated W/Rod K-2 Will Be Replaced & Rod Will Be Tested During Startup Testing
References
NUDOCS 9804220211
Download: ML20217A247 (1)
v • d • e

LER-1998-001, Forwards LER 98-001-00 Re Manual Reactor Trip Due to Dropped Control Rod K-2.Two NRC Commitments Contained in Corrective Action Section of LER

Event date:
Report date:
3641998001R00 - NRC Website
v • d • e

text

.

Dave Morey Sruth:rn Nuclear Vice President Op: rating Compa:y farley Project R0. Box 1295 Birmingham, Alabama 35201 Tel 205.992.5131 4

5 SOUTHERN COMPANY hpril 16a 1998 Energy to Serve Your World' Docket No.:.

50-364 10 CFR 50.73 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,DC 20555 Joseph M. Farley Nuclear Plant-Unit 2 Licensec Event Report No. 98-01-00 Manual Reactor Trio Due to Drooped Control Rod K-2 Ladies and Gentlemen:

Joseph M. Farley Nuclear Plant Unit 2 Licensee Event Report No. 98-01-00 is being submitted in accordance with 10 CFR 50.73. There are two NRC commitments in the Corrective Action of the License Event Report..No other commitments are contained in this submittal. Ifyou have any questions, please advise.

Respectfully submitted, (fh,7/2nt<

Dave Morey EWC/ cit:98-01-00. doc s

Enclosure b

I cc:

Mr. L. A. Reyes, Region U Administrator l

Mr. J. I. Zimmernon, NTA Project Manager

)

Mr. T. M. Ross, Plam br. Resident Inspector 9804220211 980416 gDR ADOCK 05000364 PDR

- - 'u v v. ij.

Licensee Event Report

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000364/LER-1998-001-01, :on 980328,manual Reactor Trip Was Noted.Caused by Dropped Control Rod K-2 & F-10.Affected Cable & Connectors Were Replaced During Unit 2 Twelfth Refueling Outage & Tested During Startup	on 980328,manual Reactor Trip Was Noted.Caused by Dropped Control Rod K-2 & F-10.Affected Cable & Connectors Were Replaced During Unit 2 Twelfth Refueling Outage & Tested During Startup
05000364/LER-1998-001-05, :on 980328,manual Reactor Trip Due to Dropped Control Rod K-2,was Determined.Caused by Overcurrent Condition.Crdm Cable & Connectors Associated W/Rod K-2 Will Be Replaced & Rod Will Be Tested During Startup Testing	on 980328,manual Reactor Trip Due to Dropped Control Rod K-2,was Determined.Caused by Overcurrent Condition.Crdm Cable & Connectors Associated W/Rod K-2 Will Be Replaced & Rod Will Be Tested During Startup Testing	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000364/LER-1998-001, Forwards LER 98-001-00 Re Manual Reactor Trip Due to Dropped Control Rod K-2.Two NRC Commitments Contained in Corrective Action Section of LER	Forwards LER 98-001-00 Re Manual Reactor Trip Due to Dropped Control Rod K-2.Two NRC Commitments Contained in Corrective Action Section of LER
05000348/LER-1998-001-02, :on 980217,inadequately Performed Surveillance Occurred Due to Improper Calculation of E-Bar.E-Bar & 100/E-Bar Values Were Recalculated Using Corrected Average Beta Energies for Each Unit	on 980217,inadequately Performed Surveillance Occurred Due to Improper Calculation of E-Bar.E-Bar & 100/E-Bar Values Were Recalculated Using Corrected Average Beta Energies for Each Unit
05000364/LER-1998-002-04, :on 980405,discovered Turbine Auto Stop Trip (AST) Oil Pressure Switch Sepoints Out of TS Limits.Caused by Vibration Induced Wear.Will Replace Existing AST Switches W/More Rugged Type Pressure Switch Less Susceptible to Wear	on 980405,discovered Turbine Auto Stop Trip (AST) Oil Pressure Switch Sepoints Out of TS Limits.Caused by Vibration Induced Wear.Will Replace Existing AST Switches W/More Rugged Type Pressure Switch Less Susceptible to Wear
05000364/LER-1998-002, Forwards LER 98-002-00 Re Discovery of Turbine Auto Stop Oil Pressure Switch Setpoints Being Out of TS Limits.Commitments Made by Util,Discussed	Forwards LER 98-002-00 Re Discovery of Turbine Auto Stop Oil Pressure Switch Setpoints Being Out of TS Limits.Commitments Made by Util,Discussed
05000348/LER-1998-002-05, :on 980816,SG Tube Leakage Investigation,Repair & Evaluation,Occurred.Caused by ODSCC in Two Locations on Same Tube.Operational Leak Rate Limit Requiring Plant Shutdown Has Been Administratively Reduced	on 980816,SG Tube Leakage Investigation,Repair & Evaluation,Occurred.Caused by ODSCC in Two Locations on Same Tube.Operational Leak Rate Limit Requiring Plant Shutdown Has Been Administratively Reduced	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)
05000348/LER-1998-002, Forwards LER 98-002-00 Re SG Tube Leakage Investigation Repair & Evaluation.Commitments Contained in Corrective Action Section of Event Rept,Listed	Forwards LER 98-002-00 Re SG Tube Leakage Investigation Repair & Evaluation.Commitments Contained in Corrective Action Section of Event Rept,Listed
05000348/LER-1998-003, :on 970315,failure to Comply W/Ts 4.5.3.2 & 3.5.2,was Determined.Caused by Personnel Error.Personnel Involved Have Been Coached Re Procedure Adherence	on 970315,failure to Comply W/Ts 4.5.3.2 & 3.5.2,was Determined.Caused by Personnel Error.Personnel Involved Have Been Coached Re Procedure Adherence	10 CFR 50.73(a)(2)(i)
05000364/LER-1998-003-01, :on 980411,SG Tube Degradation & Tube Status Were Noted During Insp.Caused by Tube Defects.Tubes Were Repaired & Plugged	on 980411,SG Tube Degradation & Tube Status Were Noted During Insp.Caused by Tube Defects.Tubes Were Repaired & Plugged
05000348/LER-1998-003-04, :on 980816,determined That Wgdt Hydrogen & Oxygen Had Exceeded Concentration Limits,Per TS 3.11.2.5. Caused by Undetected Leak.Leak Was Identified & Isolated & Waste Gas Sys Was Returned to Svc on 980818.With	on 980816,determined That Wgdt Hydrogen & Oxygen Had Exceeded Concentration Limits,Per TS 3.11.2.5. Caused by Undetected Leak.Leak Was Identified & Isolated & Waste Gas Sys Was Returned to Svc on 980818.With	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)
05000364/LER-1998-004-01, :on 980420,failure to Perform Penetration Room Filtration Sys SR Was Noted.Caused by Personnel Error.Note Has Been Corrected & Initial Review of Surveillance Schedules Have Been Performed	on 980420,failure to Perform Penetration Room Filtration Sys SR Was Noted.Caused by Personnel Error.Note Has Been Corrected & Initial Review of Surveillance Schedules Have Been Performed
05000364/LER-1998-004, Forwards LER 98-004-00,IAW 10CFR50.73(a)(2)(i).Commitments Made within Ltr,Listed	Forwards LER 98-004-00,IAW 10CFR50.73(a)(2)(i).Commitments Made within Ltr,Listed	10 CFR 50.73(a)(2)(i)
05000348/LER-1998-004-03, :on 980909,turbine Trip & Consequent Reactor Trip Occurred.Caused by Reactor Protection Sys Card Failure. Failed Card Was Replaced & Unit 1 Returned to Power on 980910.With	on 980909,turbine Trip & Consequent Reactor Trip Occurred.Caused by Reactor Protection Sys Card Failure. Failed Card Was Replaced & Unit 1 Returned to Power on 980910.With	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)(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)(viii)
05000364/LER-1998-005, :on 980516,noted That TS 3.0.4 Had Not Been Met During Mode Change Due to Turbine Driven Auxiliary Feedwater Pump Being Inoperable.Caused by Personnel Error.Opened Isolation Valve to Restore Tdafwp Flow Path to 2C SG	on 980516,noted That TS 3.0.4 Had Not Been Met During Mode Change Due to Turbine Driven Auxiliary Feedwater Pump Being Inoperable.Caused by Personnel Error.Opened Isolation Valve to Restore Tdafwp Flow Path to 2C SG
05000348/LER-1998-005, :on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures	on 980315,failure to Perform Nuclear Instrumentation Surveillance Requirements Prior to Mode 2 & 3 Entry,Was Discovered.Caused by Personnel Error.Revised Applicable Procedures	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) 10 CFR 50.73(s)(2)
05000348/LER-1998-005-03, :on 981021,automatic Start of B Train Penetration Room Filtration Occurred Due to Filling Sf Tc. Caused by Inadequate Procedure.Changed Procedure to Provide Specific Guidance for Filling SFP Tc.With	on 981021,automatic Start of B Train Penetration Room Filtration Occurred Due to Filling Sf Tc. Caused by Inadequate Procedure.Changed Procedure to Provide Specific Guidance for Filling SFP Tc.With
05000348/LER-1998-006-03, :on 981124,PRF Sys Suction Damper Was Outside Design & Licensing Basis.Caused by 1976 Personnel Failure to Identify Noted Inconsistency.Scheduled Design Change in 1999 to Modify Dampers to Ensure Licensing Basis Are Met	on 981124,PRF Sys Suction Damper Was Outside Design & Licensing Basis.Caused by 1976 Personnel Failure to Identify Noted Inconsistency.Scheduled Design Change in 1999 to Modify Dampers to Ensure Licensing Basis Are Met
05000348/LER-1998-006, Forwards LER 98-006-00,re PRF Sys Suction Damper Outside Design & Licensing Basis.First Paragraph in Corrective Action Section Contains NRC Commitments Associated with LER	Forwards LER 98-006-00,re PRF Sys Suction Damper Outside Design & Licensing Basis.First Paragraph in Corrective Action Section Contains NRC Commitments Associated with LER
05000364/LER-1998-006, :on 980515,containment Penetration Overcurrent Protective Device Energized.Caused by Inadequate Procedure. Motor Space Heater Breaker 2C RCP Was Promptly Opened to Restore Compliance W/Ts	on 980515,containment Penetration Overcurrent Protective Device Energized.Caused by Inadequate Procedure. Motor Space Heater Breaker 2C RCP Was Promptly Opened to Restore Compliance W/Ts	10 CFR 50.73(a)(2)(i)
05000364/LER-1998-007-01, :on 981116,ESF Actuation Occurred During DG 1000 Kw Load Rejection Test.Caused by Poor Jumper Electrical Connection.Improved Jumpers Will Be Used on Appropriate Terminals in Load Rejection Test Procedures.With	on 981116,ESF Actuation Occurred During DG 1000 Kw Load Rejection Test.Caused by Poor Jumper Electrical Connection.Improved Jumpers Will Be Used on Appropriate Terminals in Load Rejection Test Procedures.With	10 CFR 50.73(a)(2)(iv), System Actuation
05000348/LER-1998-007-02, :on 981106,found Several TSP Circumferential Indications & Several TSP Axial Indications Extending Just Beyond Edge of Tsp.Caused by Tube Defects.Sg Tubes Have Been Plugged or Repaired as Required	on 981106,found Several TSP Circumferential Indications & Several TSP Axial Indications Extending Just Beyond Edge of Tsp.Caused by Tube Defects.Sg Tubes Have Been Plugged or Repaired as Required	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000348/LER-1998-008-01, :on 981223,reactor Vessel Support Concrete Design Bases Temperature Exceeded Due to Closed Cooling Damper.Caused by Personnel Error.Damper Opened & Secured in Position.With	on 981223,reactor Vessel Support Concrete Design Bases Temperature Exceeded Due to Closed Cooling Damper.Caused by Personnel Error.Damper Opened & Secured in Position.With

Retrieved from "https://kanterella.com/w/index.php?title=05000364/LER-1998-001,_Forwards_LER_98-001-00_Re_Manual_Reactor_Trip_Due_to_Dropped_Control_Rod_K-2.Two_NRC_Commitments_Contained_in_Corrective_Action_Section_of_LER&oldid=3967223"