LER-1997-002, Forwards LER 97-002-00 Re Automatic Reactor Trip Following Spurious Opening of All Four RT Switchgear Breakers |
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CATEGORY j.
REGULAT INFORMATION DISTRIBUTIO YSTEM (RIDS)
ACCESSION NBR:9706190224 DOC.DATE: 97/06/13 NOTARIZED: NO DOCKET FACIL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION OVERBECK,G.R.
Arizona'Public Service Co.
(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards LER 97-002-00,reporting automatic RT following spurious opening of all four RT switchgear breakers.
DISTRI 9< 'I~<ib'ODE: IE22T COPIES RECEIVED: LTR ENCL SIZE:
TITLE: 50.73g50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:Standardized plant.
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05000530 T
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Palo Verde Nuclear Generating Station Gregg R. Overbeck Vice President Nuclear Production TEL 602/393.5t48 FAX 602/393.6077 Mail Station 7602 P.O. Box 52034 Phoenix, AZ 85072-2034 192-00990 -GRO/DGM/KR June 13, 1997 U. S. Nuclear Regulatory Commission ATlN: Document Control Desk Mail Station P1-37 Washington, D.C. 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 3 Docket No. STN 50-530 License No..NPF-74 Licensee Event Report 9740240 Attached please find Licensee Event Report (LER) 97-002-00 prepared and submitted pursuant to 10 CFR 50.73. This LER reports an automatic reactor trip followingthe spurious opening of all four reactor trip switchgear breakers.
In accordance with 10CFR50.73(d), a copy of this LER is being forwarded to the Regional Administrator, NRC Region IV. Ifyou have any questions, please contact Daniel G. Marks, Section Leader, Nuclear Regulatory Affairs, at (602) 393M92.
Sincerely, GRO/DGM/KR/kr Attachment cc:
E. W. Merschoff K E. Perkins F. L. Brush INPO Records Center (all with attachment) 9706i90224 9706i3 PDR ADQCK 05000530 8
PDR
~ ~ 13<,'$ fg llllllllllllllllllllllllllllllllllllllll
VERIFICATIONOF ACCURACY CRDR Investigation for 3-7-0263 2.
Unit 3 Unit logs COMMITMENT/ACTIONPLAN Stated or Im lied Address configuration, transportability, and generic issues concerning the missing jumper and improper crimping ofthe wires.
Mark Van Dop/L. Elliott CHANGES TO UFSAR None
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| 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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