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| | Title = Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601 | | | Title = Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601 |
| | Plant = | | | Plant = |
| | Reporting criterion = | | | Reporting criterion = 10 CFR 50.73(a)(2)(v) |
| | Power level = | | | Power level = |
| | Mode = | | | Mode = |
| | Docket = 05000277 | | | Docket = 05000277 |
| | LER year = 2097 | | | LER year = 1997 |
| | LER number = 3 | | | LER number = 3 |
| | LER revision = | | | LER revision = 0 |
| | Event date = | | | Event date = |
| | Report date = | | | Report date = |
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| =text= | | =text= |
| {{#Wiki_filter:. _ - . _ -, .~ | | {{#Wiki_filter:. |
| I Girrstt D. Edwtrds | | .~ |
| , Plant Manager A Peach Bottom Atomic Power Station 4 . .
| | I Girrstt D. Edwtrds Plant Manager A |
| v | | Peach Bottom Atomic Power Station 4 |
| . 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
| | v PECO NUCLEAR no ro-c-v 1848 Lay Road l |
| : U. S. Nuclear Regulatory Commission Washington, DC 20555 Docket Nos. 50-277
| | 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 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Licensee Event Report. Peach Bottom Atomic Power Station Unit 2 l | | 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 |
| I This LER concerns an inoperability of the High Pressure Coolant injection System when a l wire lug was lifted in a control circuit.
| | wire lug was lifted in a control circuit. |
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| ==Reference:== | | ==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 | | Docket No. 50-277 Report Number 2-97-003 Revision Number: |
| : Sincerely, s
| | 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 | | GDE/GAJ:gaj 4 |
| enclosure l l 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 R. l. McLean, State of Maryland ~ 3 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 | | 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 |
| }} | | }} |
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| {{LER-Nav}} | | {{LER-Nav}} |
LER-1997-003, Forwards LER 97-003-00,concerning Inoperability of Hpcis When Wire Lug Was Lifted in Control Circuit on 970601 |
| Event date: |
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| Report date: |
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| Reporting criterion: |
10 CFR 50.73(a)(2)(v), Loss of Safety Function |
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| 2771997003R00 - NRC Website |
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text
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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
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| | | Reporting criterion |
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| 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 | |
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