LER-1997-002, Forwards LER 97-002-00,reporting Violation of TS Due to Missing Performance of SR for Core Protection Calculators |
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ACCESSION NBR:9707150356 DOC.DATE: 97/07/ 07 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 AUTH. iNAME AUTHOR AFFILIATION OVERBECK,G.R.
Arizona Public Service Co.
(formerly Arizona Nuclear Power RECIP.NAlIE RECIPIENT AFFILIATION Document Control Branch (Document Control Desk,).
SUBJECT:
Forwards LER 97-002-00,reporting violation of TS due to missing performance of SR for core protection calculators.
DISTRIBUTION CODE:
IE22T COPIES RECEIVED:LTR 2 ENCLi SIZE:
I +
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:STANDARDIZED PLANT 05000528 T
RECIPIENT ID CODE/NAME PD4-2 PD INTERNAL: ACRS
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1 RECIPIENT ID CODE/NAME THOMASFK A
PD RAB IL CENT B
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NOAC QUEENER,DS NUDOCS FULL TXT COPIES LTTR ENCL 1
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NOTE TO ALL MRZDS" RECZPZENTS:
PLEASE HELP US TO REDUCE WASTEl CONTACT THE DOCUMENT CONTROL DESK,,
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Palo Verde Nuclear Generating Station Gregg R. Overbeck Vice President Nuclear Production TEL 602/393-5148 FAX 602/393-6077 Mail Station 7602 P.O. Box 52034 Phoenix, AZ 85072-2034 192-00995 - GRO/DGM/KR July 7, 1997 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, D.C. 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528 License No. NPFC1 Licensee Event Report 9740240 Attached please find Licensee Event Report (LER) 97-002%0 prepared and submitted pursuant to 10 CFR 50.73. This LER reports a violation ofTechnical-Specifications due to missing the performance of a surveillance requirement for core protection calculators.
In accordance with 10CFR50.73(d), a copy ofthis 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 9707i 50356 970707 PDR ADOCK 05000528 8
PDR
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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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