LER-1996-003, Forwards LER 96-003-01 Per 10CFR50.73.Commitments Made in Crdr 160156 Included |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 5281996003R01 - NRC Website |
|
text
CATEGORY REGULATO INFORMATION DISTRIBUTION'TEM (RIDS)
ACCESSION, NBR:9705210004 DOC.DATE: 97'/05/09 NOTARIZED: NO DOCKET ¹ FACIAL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 AUTH.NAME AUTHOR AFFILIATION
'OVERBECK,G.R.
Arizo'na Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch
(.Document Control Desk)
SUBJECT:
Forwards LER 96-003-01 per 10CFR50.73.Commitments made in CRDR 160156 included.
DISTRIBUTION CODE:
IE22T COPIES. RECEIVED:LTR I
ENCL J SIZE: Z TITLE: 50.73/50.,9'icensee Event Report (LER), incident Rpt, etc.
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 POORE,W.
NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME CLIFFORD,J A 0 E, CENT DE EELB.
NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN4 FILE 01 LITCO BRYCE,J H
NOAC QUEENER,DS 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 05000528 E.
0 Y
D N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 25.
ENCL 25
II
. Ctj,.',
Ca'nrmirmenr./nemilaa fnergy.
Paio Verde Nucfear 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 U. S. Nuclear Regulatory Commission ATlN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001, 192-00989 -GRO/DGM/RJH May 9, 1997
Dear Sirs:
Subject:
Palo Verde Nuclear, Generating Station (PVNGS)
Unit 1 Docket. No. STN,50-528 License No. NPFQ1 Licensee Event Report 96-003-01 Attached please find Supplement 1 to Licensee Event Report (LER)96-003 prepared and submitted pursuant to 10CFR50.73.
This LER reports the August 9,
1996 discovery that Trains A and B Fuel Building Essential Filtration units were rendered inoperable when a control. door in the Auxiliary Building was propped open.
ln accordance with 10CFR50.73(d), a copy of this LER is being forwarded to the Regional Administrator, NRC Region IV.
lf you have any questions, please contact Daniel G. Marks, Section Leader, Nuclear Regulatory Affairs, at (602) 393-,6492.
Sincerely, GRO/DGM/RJH/rlh CC:
E. W. Merschoff K. E. Perkins K. E. Johnston INPO Records Center
'P7052i0004
'P70509-PDR ADQCK 05000528 8
PDR
~ggO lllllllllllllllllllllllllilliill!
IIIIIII
41 II
NRC Document Control Desk Supplement 1 to LER 96-003-00 Page 3 INTERNALDISTRIBUTIONONLY VERIFICATIONOF ACCURACY 10CFR50.73'Licensee Event Report 2.
HPES 160156 3.
Procedure 40DP-9ZZ17, Rev. 8, "Control of Doors, Matches and Floor Plugs" 4.
CRDR 160156 5.
DMWO 00769396 6.
NRC Inspection Report 50-528/529/530/96-13 7.
LER 1-96-003-00 INTERNALDISTRIBUTIONONLY COMMITMENTSMADE IN CRDR 160156
- 1) Design Modification Work Order (DMWO) 00769396 willbe implemented to install all appropriate signage in all three units and is expected to be completed by April 1997.
- 2) A multi-discipline evaluation of door design willcontinue and any discrepancies willbe evaluated and be incorporated into the door procedure.
- 3) Appropriate station personnel willbe trained. on any changes to procedure 40DP-9ZZ17 resulting from the ongoing evaluation.
CHANGES TO UFSAR None
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000528/LER-1996-001, Forwards LER 96-001-00 Re Identification of Condition Resulting in Being Outside Design Basis of Plant,Could Have Adversely Affected Ability to Achieve & Maintain Safe Shutdown Conditions,Per PVNGS Fire Protection Program | Forwards LER 96-001-00 Re Identification of Condition Resulting in Being Outside Design Basis of Plant,Could Have Adversely Affected Ability to Achieve & Maintain Safe Shutdown Conditions,Per PVNGS Fire Protection Program | | | 05000528/LER-1996-001-01, Documents Conversation Between Util & D Kirsch on 960726 Re Commitment Update for LER 96-001-01 | Documents Conversation Between Util & D Kirsch on 960726 Re Commitment Update for LER 96-001-01 | | | 05000530/LER-1996-001-02, :on 960621,inaccurate Gas Calculations for Post Accident Sampling Sys Occurred.Caused by Surveillance Test Worksheet Errors.Independent Investigation of Event Being Conducted |
- on 960621,inaccurate Gas Calculations for Post Accident Sampling Sys Occurred.Caused by Surveillance Test Worksheet Errors.Independent Investigation of Event Being Conducted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000528/LER-1996-002-02, :on 960514,Tech Spec Violation Occurred Due to Erroneous Surveillance Requirement.Caused by Incorporation of C-E Generic Ts.Investigation Being Conducted |
- on 960514,Tech Spec Violation Occurred Due to Erroneous Surveillance Requirement.Caused by Incorporation of C-E Generic Ts.Investigation Being Conducted
| 10 CFR 50.73(a)(2) | | 05000529/LER-1996-002, :on 960401,inappropriate Work Practice Resulted in Esfa of Train B Edg.Night Order Was Issued to All Three Units Describing Event |
- on 960401,inappropriate Work Practice Resulted in Esfa of Train B Edg.Night Order Was Issued to All Three Units Describing Event
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000528/LER-1996-003, Forwards LER 96-003-00 Prepared & Submitted Pursuant to 10CFR50.73.LER Reports TS Violation Involving Nuclear Power Channel Calibrations,Due to Precedural Deficiency | Forwards LER 96-003-00 Prepared & Submitted Pursuant to 10CFR50.73.LER Reports TS Violation Involving Nuclear Power Channel Calibrations,Due to Precedural Deficiency | | | 05000529/LER-1996-003, :on 960122,missed Surveillance for Logic Check of Logs 1 & 2 Safety Excore Bypasses.Caused by Procedural Error.Log Power Functional Test Revised to Check Logs 1 & 2 Bypasses Regardless of Power Level |
- on 960122,missed Surveillance for Logic Check of Logs 1 & 2 Safety Excore Bypasses.Caused by Procedural Error.Log Power Functional Test Revised to Check Logs 1 & 2 Bypasses Regardless of Power Level
| | | 05000528/LER-1996-003-01, Forwards LER 96-003-01 Per 10CFR50.73.Commitments Made in Crdr 160156 Included | Forwards LER 96-003-01 Per 10CFR50.73.Commitments Made in Crdr 160156 Included | | | 05000529/LER-1996-005, :on 960628,inadequate Procedural Controls Allows Equipment Qualification Boundary to Be Breached. Caused by Lack of Procedural Controls Placed on Use of Personnel Hatch.Personnel Hatch Closed |
- on 960628,inadequate Procedural Controls Allows Equipment Qualification Boundary to Be Breached. Caused by Lack of Procedural Controls Placed on Use of Personnel Hatch.Personnel Hatch Closed
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)
10 CFR 50.73(s)(2)(v) | | 05000528/LER-1996-007, :on 961119,surveillance Test Deficiencies Were Found During GL 96-01 Review Leading to TS 3.0.3 Entries. Caused by Increase in Scope of Required Testing.Supplement Will Be Submitted |
- on 961119,surveillance Test Deficiencies Were Found During GL 96-01 Review Leading to TS 3.0.3 Entries. Caused by Increase in Scope of Required Testing.Supplement Will Be Submitted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2) | | 05000528/LER-1996-008, :on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised |
- on 960507,inadequate Procedure Results in Nuclear Power Channels Not Calibrated During Power Ascension Tests Occurred.Caused by Deficient Procedure.Procedure Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000528/LER-1996-009, :on 961027,identified That TS Violation May Have Occurred Due to Missed Surveillance Test.Caused by Personnel Error.Setpoint for Limit Switches for Valve 1SIAUV647 Corrected to Achieve 1-inch Stroke Length |
- on 961027,identified That TS Violation May Have Occurred Due to Missed Surveillance Test.Caused by Personnel Error.Setpoint for Limit Switches for Valve 1SIAUV647 Corrected to Achieve 1-inch Stroke Length
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) |
|
