05000277/LER-1997-003, Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601

From kanterella

(Redirected from ML20141G531)

Jump to navigation Jump to search

Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601
Person / Time
ML20141G531
Site:	Peach Bottom
Issue date:	06/27/1997
From:	Geoffrey Edwards PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20141G535	List: 05000277/LER-1997-003, Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601 05000277/LER-1997-003-03, :on 970601,HPCI Was Inoperable.Caused by Lifting of Common Power Wire Lug in HPCI Electrical Power Logic as Part of GP-25 Activity.Hpci Sys Was Restored to Operable Condition
References
NUDOCS 9707090249
Download: ML20141G531 (1)
v • d • e

LER-1997-003, Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function
2771997003R00 - NRC Website
v • d • e

text

.

.~

I Girrstt D. Edwtrds Plant Manager A

Peach Bottom Atomic Power Station 4

v PECO NUCLEAR no ro-c-v 1848 Lay Road l

A UMr or PECO ENtscy Detta. PA 17314-9032 717 456 4244 Document Control Desk June 27, 1997 U. S. Nuclear Regulatory Commission Washington, DC 20555 Docket Nos. 50-277

SUBJECT:

Licensee Event Report. Peach Bottom Atomic Power Station Unit 2 This LER concerns an inoperability of the High Pressure Coolant injection System when a l

wire lug was lifted in a control circuit.

Reference:

Docket No. 50-277 Report Number 2-97-003 Revision Number:

00 Event Date:

6/1/97 Report Date:

6/27/97 Facility:

Peach Bottom Atomic Power Station 1848 Lay Road, Delta, PA 17314 This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(v).

i Sincerely, s

GDE/GAJ:gaj 4

l enclosure cc:

W. T. Henrick, Public Service Electric & Gas R. R. Janati, Commonwealth of Pennsylvania l

INPO Records Center H. J. Miller, US NRC, Administrator, Region 1 3

R. l. McLean, State of Maryland

~

W. L. Schmidt, US NRC, Senior Resident Inspector A. F. Kirby lil, DelMarVa Power T.M.Messick, Atlantic Electric 9707090249 970627 PDR ADOCK 05000277 CCN 97-14039

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
05000277/LER-1997-001-03, :on 970318,TS Violation Due to non-conservative Average Power Range Monitor Flow Bias Scram Setpoints for Single Loop Operation.Procedural Enhancements to Ensure That Single Loop Flow Conditions,Accommodated	on 970318,TS Violation Due to non-conservative Average Power Range Monitor Flow Bias Scram Setpoints for Single Loop Operation.Procedural Enhancements to Ensure That Single Loop Flow Conditions,Accommodated	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1)
05000278/LER-1997-001, :on 970122,determined Plant Thermal Power Exceeded 100% Due to Out of Tolerance Test Equipment.Retired Test Apparatus from Future Use & Will Review and Revise Procedures for Feedwater Temp Instruments	on 970122,determined Plant Thermal Power Exceeded 100% Due to Out of Tolerance Test Equipment.Retired Test Apparatus from Future Use & Will Review and Revise Procedures for Feedwater Temp Instruments	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000277/LER-1997-002-03, :on 970326,TS Violation Identified as Result of Reactor Operation Slightly in Excess of Licensed Thermal Power.Ctp Calculation Program Was Modified to Compensate for Recirculation Pump Motor Power Factor	on 970326,TS Violation Identified as Result of Reactor Operation Slightly in Excess of Licensed Thermal Power.Ctp Calculation Program Was Modified to Compensate for Recirculation Pump Motor Power Factor	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000278/LER-1997-002-02, :on 970309,manual Scram Occurred Due to Loss of Forced Reactor Core Circulation at Power as Result of 13kv Feeder Breaker Auxiliary Switch Failure.Auxiliary Switch Assembly Was Cleaned & Lubricated	on 970309,manual Scram Occurred Due to Loss of Forced Reactor Core Circulation at Power as Result of 13kv Feeder Breaker Auxiliary Switch Failure.Auxiliary Switch Assembly Was Cleaned & Lubricated	10 CFR 50.73(a)(2)(iv), System Actuation
05000277/LER-1997-003, Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601	Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000277/LER-1997-003-03, :on 970601,HPCI Was Inoperable.Caused by Lifting of Common Power Wire Lug in HPCI Electrical Power Logic as Part of GP-25 Activity.Hpci Sys Was Restored to Operable Condition	on 970601,HPCI Was Inoperable.Caused by Lifting of Common Power Wire Lug in HPCI Electrical Power Logic as Part of GP-25 Activity.Hpci Sys Was Restored to Operable Condition	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
05000278/LER-1997-003-01, :on 970404,TS Noncompliance Due to Loss of 3C RFP High Water Level Trip,Occurred.Caused by Failure to Correlate Turbine/Reset Light Problem to Inoperability. Operating Shift Procedures Revised	on 970404,TS Noncompliance Due to Loss of 3C RFP High Water Level Trip,Occurred.Caused by Failure to Correlate Turbine/Reset Light Problem to Inoperability. Operating Shift Procedures Revised	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000277/LER-1997-004-02, :on 970710,discovered non-compliance W/Ts When TS Action Times Were Exceeded.Caused by Procedural Control Not Being Adequate to Ensure Radiation Monitor Would Be Maintained in Trip Condition.Made Rev to GP-25 App 13 & 14	on 970710,discovered non-compliance W/Ts When TS Action Times Were Exceeded.Caused by Procedural Control Not Being Adequate to Ensure Radiation Monitor Would Be Maintained in Trip Condition.Made Rev to GP-25 App 13 & 14	10 CFR 50.73(a)(2)(i)
05000277/LER-1997-004, Forwards LER 97-004-00 Re non-compliance of MCR Emergency Ventilation Sys TS Which Occurred on 970710	Forwards LER 97-004-00 Re non-compliance of MCR Emergency Ventilation Sys TS Which Occurred on 970710	10 CFR 50.73(a)(2)(i)
05000277/LER-1997-005-02, :on 970808,discovered TS non-compliance Associated W/Rod Block Contact Testing.Caused by Rev in Oct 1989,attempted to Consolidate Testing of Rod Block Logic from Two Instrument Panels.Procedure Revised	on 970808,discovered TS non-compliance Associated W/Rod Block Contact Testing.Caused by Rev in Oct 1989,attempted to Consolidate Testing of Rod Block Logic from Two Instrument Panels.Procedure Revised	10 CFR 50.73(a)(2)(i)
05000277/LER-1997-006, Forwards LER-97-006-00,concerning Unplanned ESF Actuation During 4-kV Electrical Bus Relay Testing Activities on 970923	Forwards LER-97-006-00,concerning Unplanned ESF Actuation During 4-kV Electrical Bus Relay Testing Activities on 970923	10 CFR 50.73(a)(2)(iv), System Actuation
05000277/LER-1997-006-02, :on 970923,DG Auto Start During 4-kV Relay Testing Occurred.Caused by Personnel Error.Need for Exercising Caution When Removing or Installing Relay Cover Was Discussed W/I&C Technicians	on 970923,DG Auto Start During 4-kV Relay Testing Occurred.Caused by Personnel Error.Need for Exercising Caution When Removing or Installing Relay Cover Was Discussed W/I&C Technicians	10 CFR 50.73(a)(2)(iv), System Actuation
05000277/LER-1997-007, Forwards LER 97-007-00 Which Documents Event That Occurred at Peach Bottom Atomic Power Station,Units 2 & 3 on 740705	Forwards LER 97-007-00 Which Documents Event That Occurred at Peach Bottom Atomic Power Station,Units 2 & 3 on 740705	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000277/LER-1997-007-02, :on 970821,engineering Personnel Identified Potential Suppression Chamber Steam Bypass Leakage Path Between Air Spaces of Drywell & Torus.Caused by Original Design Deficiency.Drywell Purge Supply Valve Disabled	on 970821,engineering Personnel Identified Potential Suppression Chamber Steam Bypass Leakage Path Between Air Spaces of Drywell & Torus.Caused by Original Design Deficiency.Drywell Purge Supply Valve Disabled	10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
05000277/LER-1997-008, Forwards LER 97-008-00,reporting Discovery of safety-related Logic Components That Were Not Tested Per TS Surveillance Requirements on 740705	Forwards LER 97-008-00,reporting Discovery of safety-related Logic Components That Were Not Tested Per TS Surveillance Requirements on 740705	10 CFR 50.73(a)(2)(1)
05000277/LER-1997-008-02, :on 740705,logic Sys Functional Testing Did Not Contain All Required Testing Per TS Surveillance Requirements.Caused by Test Procedures Not Containing Required Testing.Untested Contacts Tested & Proved Operable	on 740705,logic Sys Functional Testing Did Not Contain All Required Testing Per TS Surveillance Requirements.Caused by Test Procedures Not Containing Required Testing.Untested Contacts Tested & Proved Operable	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000277/LER-1997-009-01, Forwards LER 97-009-01,reporting Reactor Scram on 971109, Resulting from Generator Lockout Condition & Subsequent Turbine Trip.Rev to Original Submittal & Discussion Anomalies Found w/2A Reactor Feedpump Turbine Trip Sys	Forwards LER 97-009-01,reporting Reactor Scram on 971109, Resulting from Generator Lockout Condition & Subsequent Turbine Trip.Rev to Original Submittal & Discussion Anomalies Found w/2A Reactor Feedpump Turbine Trip Sys	10 CFR 50.73(a)(2)(iv), System Actuation
05000277/LER-1997-009, :on 971109,reactor Scram Occurred.Caused by Generator Lockout Condition & Subsequent Turbine Trip Failure of 2A Reactor Feedpump Turbine to Trip on Demand During Recovery Activities.Reset Appropriate Scram Logics	on 971109,reactor Scram Occurred.Caused by Generator Lockout Condition & Subsequent Turbine Trip Failure of 2A Reactor Feedpump Turbine to Trip on Demand During Recovery Activities.Reset Appropriate Scram Logics	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)
05000277/LER-1997-009-02, :on 971109,generator Lockout & Subsequent Turbine Trip Occurred.Caused by Turbine Trip Resulting from Generator Lockout Signal.Appropriate PCIS & RPS Scram Logics Were Reset	on 971109,generator Lockout & Subsequent Turbine Trip Occurred.Caused by Turbine Trip Resulting from Generator Lockout Signal.Appropriate PCIS & RPS Scram Logics Were Reset	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000277/LER-1997-010-02, :on 971229,2A RFPT Failed to Trip When RO Pushed CR 2A RFPT Trip push-button.Caused by Intermittent Failure Mechanism.Repaired,Reinstalled & Tested Operability of 2A RFPT	on 971229,2A RFPT Failed to Trip When RO Pushed CR 2A RFPT Trip push-button.Caused by Intermittent Failure Mechanism.Repaired,Reinstalled & Tested Operability of 2A RFPT	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i)
05000277/LER-1997-010, :on 971229,failure of 2A Reactor Feedpump Turbine to Trip,Occurred.Caused by Main Control Room pushbutton.2A RFPT Trip Device Repaired,Reinstalled & Tested to Prove Operability	on 971229,failure of 2A Reactor Feedpump Turbine to Trip,Occurred.Caused by Main Control Room pushbutton.2A RFPT Trip Device Repaired,Reinstalled & Tested to Prove Operability	10 CFR 50.73(a)(2)
05000277/LER-1997-010-01, Forwards LER 97-010-01,reporting 971229 Failure of 2A Reactor Feedpump Turbine to Trip in Timely Manner	Forwards LER 97-010-01,reporting 971229 Failure of 2A Reactor Feedpump Turbine to Trip in Timely Manner

Retrieved from "https://kanterella.com/w/index.php?title=05000277/LER-1997-003,_Forwards_LER_97-003-00,concerning_Inoperability_of_Hpcis_When_Wire_Lug_Was_Lifted_in_Control_Circuit_on_970601&oldid=4186236"