LER-1997-003, Forwards LER 97-003-00 Re Inadequate Protection Against Floodwater Migration Due to Construction Design Deficiency. Commitments Made by Util,Encl |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 5281997003R00 - NRC Website |
|
text
CATEGORY 1 REGULATO INFORMATION DISTRIBUTION STEM (RIDS) 0 ACCESSION NBR:9709030196 DOC.DATE: 97/08/22 NOTARIZED:.NO DOCKET I FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 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 97-003-00 re inadequate protection against floodwater migration due to construction design deficiency.
Commitments
made by uti;l,encl.
DISTRIBUTION CODE:
IE22T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: 50.,73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:STANDARDIZED PLANT T
05000528 RECIPIENT ID CODE/NAME PD4-2 PD COPIES LTTR ENCL 1
1 RECIPIENT COPIES ID CODE/NAME LTTR ENCL THOMAS,K 1
1 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 POORE,W.
NRC PDR 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 E-
.SPD/
.. B FILE CERATE NRR/DE/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN4 FILE 01 LITCO BRYCEiJ H
NOAC QUEENERiDS NUDOCS FULL TXT 2
2 1
1 1
1 1
1 1
1 1
1 1
l.
1 1
1 1
1 1
1 1
D 0
U M
E N
NOTE TO ALL "RZDS" RECIPIENTS:
PLEAsE HELP Us To REDUcE wAsTE. To HAvE YoUR NAME oR QRGANIZATIQN REMovED FRoM DISTRIBUTIoN LzsTs OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 25 ENCL 25
i)
I I
ply
'oailn/remt.lnemtkn &egy.
Palo Verde Nuctear Generating Station Gregg R. Overbeck Vice President Nuclear Production TEL 602/393-5148 FAX 602/3936077 Mail Station 7602 P.O. Box 52034 Phoenix, AZ 85072-2034 102-03995 -GRO/DGM/REB August 22, 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)
Units 1, 2, and 3 Docket Nos. STN 50-628/529/630 License No. NPFP1/51/74 Licensee Event Report 97-003-00 Attached please. find Licensee Event Report (LER) 97-003-00 prepared and submitted pursuant to 10 CFR 50.73.
This LER reports a condition where a construction design deficiency resulted in inadequate protection against floodwater migration.
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) 393-6492.
Sincerely, GRO/DGM/REB/mah Attachment cc:
E. W. Merschoff K. E. Perkins PVNGS Sr. Resident INPO Records Ceqtett.; "-;
~
~ wJ (all with attachment)
'IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII 9709030i96 970822 PDR ADQCK '05000528 S
PDR
1
U. S. N'uclear Regulatory Commission AWN: Document Control Desk Licensee Event Report 1-97-003-00 Page 3 VERIFICATIONOF ACCURACY 1.
CRDR Investigation for 1-6-0236 2.
Letter 456-00199-(Steve Kesler)
COMMITMENT/ACTIONPLAN Stated or Im lied
- 1. Appropriate Erickson fittings were sealed in the
- MSSS, Auxiliary and Control
. buildings in all three units to prevent floodwater migration to the lower levels.
DFWOs:
00774071 00774056 00774058 00774829 00775043 00775045 00774801 00775038 00775044
- 2. Appropriate drawings have been revised to provide for the current proper. sealing of Erickson fittings following maintenance, modifications and new construction.
Engineering Document Changes (EDC) 96-00943, 96-00944 for 13-A-ZZD-002 (Rev. 17) 96-00945 Engineering Document Changes 96-0943 96-01007 for 13-E-ZAC-050 CHANGES TO UFSAR None
0
~ '
|
|---|
|
|
| | | 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) |
|