05000528/LER-1997-006, Forwards LER 97-006-00,which Reports Violation of TS Due to Missing Performance of SR for ASME Section XI ISI Pressure Test

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Forwards LER 97-006-00,which Reports Violation of TS Due to Missing Performance of SR for ASME Section XI ISI Pressure Test
Person / Time
ML17313A202
Site:	Palo Verde
Issue date:	02/05/1998
From:	Overbeck G ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17313A203	List: 05000528/LER-1997-006, Forwards LER 97-006-00,which Reports Violation of TS Due to Missing Performance of SR for ASME Section XI ISI Pressure Test 05000528/LER-1997-006-01, :on 971028,missed TS 4.0.5 SR Was Noted.Caused by Personnel Error.Independent Investigation of Event Is Being Conducted IAW W/Aps Corrective Action Program
References
192-01010-GRO-D, 192-1010-GRO-D, NUDOCS 9802130057
Download: ML17313A202 (2)
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LER-1997-006, Forwards LER 97-006-00,which Reports Violation of TS Due to Missing Performance of SR for ASME Section XI ISI Pressure Test

Event date:
Report date:
5281997006R00 - NRC Website
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text

Palo Verde Nuclear Generating Station Gregg R. Overbeck Vice President Nuclear Production TEL 602I3934148 FAX 602J3936077 Mail Station 7602

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Box 52034 Phoenix, AZ85072-2034 192-01010 -GRO/DGM/KR February 5, 1998 U..S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P17 Washington, D.C. 205554001.

Dear Sirs:

'I

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50428/529/530 License Nos. NPF41/51/74 Licensee Event Report 9740640 Attached please. find Licensee Event, Report (LER) 97-0(&00 prepared and submitted pursuant.to 10CFR50.73.

This LER reports a violation of Technical Specification due to missing the performance of a surveillanc'e requirement for.an ASME Section XI inservice inspection pressure test..ln accordance with 10CFR50.73(d),*a copy of'this LER is being forwarded to the Regional Administrator,NRC Region IV.

'If you have any questions, please contact Daniel G. Marks; Section Leader,. Nuclear Regulatory Affairs, at (602) 393-6492.

Sincerely, GRO/DGM/KR/mah Attachment cc: '. W. Merschoff K E. Perkins J.'H. Moorman INPO.Records Center (all with attachment) 9802130057 980205 Art PDR'DOCK 05000528<

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Licensee Event Report

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		Reporting criterion
05000530/LER-1997-001, :on 970306,initiated Manual Fuel Bldg Essential Ventilation Actuation.Caused by Loss of Spent Fuel Pool (SPF) Level.Restored Air Pressure to Gate Seal & SPF Level Proceeded to Increase	on 970306,initiated Manual Fuel Bldg Essential Ventilation Actuation.Caused by Loss of Spent Fuel Pool (SPF) Level.Restored Air Pressure to Gate Seal & SPF Level Proceeded to Increase	10 CFR 50.73(a)(2)
05000530/LER-1997-002, Forwards LER 97-002-00 Re Automatic Reactor Trip Following Spurious Opening of All Four RT Switchgear Breakers	Forwards LER 97-002-00 Re Automatic Reactor Trip Following Spurious Opening of All Four RT Switchgear Breakers
05000528/LER-1997-002, Forwards LER 97-002-00,reporting Violation of TS Due to Missing Performance of SR for Core Protection Calculators	Forwards LER 97-002-00,reporting Violation of TS Due to Missing Performance of SR for Core Protection Calculators
05000528/LER-1997-002-02, :on 970528,SR for Core Protection Was Not Performed Due to Inadequate Procedures.Revised Procedures	on 970528,SR for Core Protection Was Not Performed Due to Inadequate Procedures.Revised Procedures	10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)
05000530/LER-1997-002-01, :on 970531,RT Occurred.Caused by Spurious Opening of All Four RT Switchgear Breakers.Independent Investigation of Event Being Conducted in Accordance W/Util Corrective Action Program	on 970531,RT Occurred.Caused by Spurious Opening of All Four RT Switchgear Breakers.Independent Investigation of Event Being Conducted in Accordance W/Util Corrective Action Program	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(4)
05000530/LER-1997-003-01, Forwards LER 97-003-01,reporting Test Results of Main Steam Safety Valve as-found Lift Settings That Were Out of Tolerance Limits Specified in TS Limiting Condition for Operation 3.7.1.1	Forwards LER 97-003-01,reporting Test Results of Main Steam Safety Valve as-found Lift Settings That Were Out of Tolerance Limits Specified in TS Limiting Condition for Operation 3.7.1.1
05000529/LER-1997-003-02, :on 970907,inadvertent Loss of Power & EDG Start Occurred Due to Procedural Error.Changed Train a & Train B Edg/Ist ST Procedures to Consistently Reflect Proper Pretest Staging Hand Switches	on 970907,inadvertent Loss of Power & EDG Start Occurred Due to Procedural Error.Changed Train a & Train B Edg/Ist ST Procedures to Consistently Reflect Proper Pretest Staging Hand Switches	10 CFR 50.73(a)(2)(iv), System Actuation
05000530/LER-1997-003, :on 970215,seven Main Steam Safety Valves Were Found Out of Tolerance Prior to Refueling Outage.Safety Analysis Performed Based Upon as-found MSSV Data Which Demonstrated That MSSVs Would Perform Safety Functions	on 970215,seven Main Steam Safety Valves Were Found Out of Tolerance Prior to Refueling Outage.Safety Analysis Performed Based Upon as-found MSSV Data Which Demonstrated That MSSVs Would Perform Safety Functions	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000528/LER-1997-003, Forwards LER 97-003-00 Re Inadequate Protection Against Floodwater Migration Due to Construction Design Deficiency. Commitments Made by Util,Encl	Forwards LER 97-003-00 Re Inadequate Protection Against Floodwater Migration Due to Construction Design Deficiency. Commitments Made by Util,Encl
05000528/LER-1997-004, Forwards LER 97-004-00 Re Inverters for Class 1E 120 Vac Vital Instrument Distribution Buses & Inverters for Class 1E 125 Vdc Buses Which Were Not in Compliance W/Seismic Design Requirements	Forwards LER 97-004-00 Re Inverters for Class 1E 120 Vac Vital Instrument Distribution Buses & Inverters for Class 1E 125 Vdc Buses Which Were Not in Compliance W/Seismic Design Requirements
05000529/LER-1997-004, Forwards LER 97-004-00,reporting TS Violation Involving Missed Neutron Flux Power Daily Channel Checks Due to Procedural Deficiency	Forwards LER 97-004-00,reporting TS Violation Involving Missed Neutron Flux Power Daily Channel Checks Due to Procedural Deficiency
05000528/LER-1997-005, Forwards LER 97-005-00,re Violation of TS SR 4.5.2.c.2 Resulting from Inadequate Procedural Impact Review of TS Amend	Forwards LER 97-005-00,re Violation of TS SR 4.5.2.c.2 Resulting from Inadequate Procedural Impact Review of TS Amend
05000528/LER-1997-006, Forwards LER 97-006-00,which Reports Violation of TS Due to Missing Performance of SR for ASME Section XI ISI Pressure Test	Forwards LER 97-006-00,which Reports Violation of TS Due to Missing Performance of SR for ASME Section XI ISI Pressure Test
05000529/LER-1997-006, :on 971020,manual Reactor Trip Occurred Due to Vibration & Bearing Temp Increases in Reactor Coolant Pump. Caused by Failed Lower Journal Bearing.Bearing Assembly Was Disassembled,Inspected & Rebuilt	on 971020,manual Reactor Trip Occurred Due to Vibration & Bearing Temp Increases in Reactor Coolant Pump. Caused by Failed Lower Journal Bearing.Bearing Assembly Was Disassembled,Inspected & Rebuilt
05000528/LER-1997-006-01, :on 971028,missed TS 4.0.5 SR Was Noted.Caused by Personnel Error.Independent Investigation of Event Is Being Conducted IAW W/Aps Corrective Action Program	on 971028,missed TS 4.0.5 SR Was Noted.Caused by Personnel Error.Independent Investigation of Event Is Being Conducted IAW W/Aps Corrective Action Program	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 10 CFR 50.73(s)(2)
05000529/LER-1997-007, :on 971006,TS Violation Occurred Due to Inadequate Shutdown Cooling Flow During Modes 5 & 6 Operation.Independent Investigation of Event Was Conducted IAW APS CA Program	on 971006,TS Violation Occurred Due to Inadequate Shutdown Cooling Flow During Modes 5 & 6 Operation.Independent Investigation of Event Was Conducted IAW APS CA Program	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)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)

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