LER-1997-003, 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 |
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| 5301997003R01 - NRC Website |
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,CATiaORY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9710060396 DOC.DATE: 97/09/26 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 AFFIIIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards LER 97-003-0l,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.
DISTRIBUTION CODE:
IE22T COPIES RECEIVED:LTR l ENCL SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
I NOTES:Standardized plant.
RECIPIENT ID CODE/NAME PD4-2 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POOREgW
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NRC PDR COPIES RECIPIENT LTTR ENCL ID CODE/NAME 1
1 THOMAS,K 1
EO~D'.SP~DRAB 1
1 NRR/DE/EELB 1
NRR/DRCH/HHFB 1
NRR/DRCH/HOLB 1
NRR/DRPM/PECB 1
NRR/DSSA/SRXB 1
RGN4 FILE 01 1
1 LITCO BRYCEiJ H 1
1 NOAC QUEENER,DS 1
1 NUDOCS FULL TXT, COPIES LTTR ENCL 1
1 2
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 05000530 6
0 D
0 C
l U
N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 41S-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 25 ENCL 25
Cnmmltmnnt. InnnrntlntLEnemy.
Palo Verde Nuclear Generating Station Gregg R. Overbeck Vice President Nuclear Production Mail Station 7602 TEL 602/393-5t48 P.O. Box 52034 FAX 602/393-6077 Phoenix, AZ85072-2034 192-00999 - GRO/DGM/RAS September 26, 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 3 Docket No. STN 50-530 License No. NPF-74 Licensee Event Report 9740341 Attached please find Supplement 1 to Licensee Event Report (LER) 97-003-00 prepared and submitted pursuant to 10 CFR 50.73.
This LER reports the test results of Main Steam Safety Valve as-found liftsettings that were out of the tolerance limits specified in Technical Specification Limiting Condition for Operation 3.7.1.1.
In accordance with 10 CFR50.73(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/RAS/rlh Attachment cc:
E. W. Merschoff K. E. Perkins J. H. Moorman INPO Records Center 97i0060396 970926 PDR ADOCK 05000530 S
PDR (all with attachment) lllllllllllllllllllllilillllllllllll
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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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