Corrected Copy of Letter for LER 03-003-00 for Palo Verde, Unit 2
Person / Time
ML040500240
Site:	Palo Verde
Issue date:	01/21/2004
From:	Danni Smith Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
192-01133-DMS/SAB/DGM/DFH LER 03-003-00
Download: ML040500240 (1)
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LER-2003-003, Corrected Copy of Letter for LER 03-003-00 for Palo Verde, Unit 2

Event date:
Report date:
5292003003R00 - NRC Website
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CORRECTED COPY - Letter date - (year only)

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A_s Palo Verde Nuclear Generating Station David M. Smith Plant Manager 1 OCFR50.73 Tel: 623-393-6116 Mail Station 7602 Fax: 623-393-6077 PO Box 52034 e-mail:

Phoenix, Arizona 85072-2034 DSMITH10@apsc.com 192-01133-DMS/SAB/DGM/DFH JanuaFy 21, 2003 January 21, 2004 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Unit 2 Docket No. STN 50-529 License No. NPF-51 Licensee Event Report 2003-003-00 Attached, please find Licensee Event Report (LER) 50-529/2003-003-00 that has been prepared and submitted pursuant to 10CFR50.73. The LER reports a condition where a Source Range Monitor was inoperable at the start of core reload while loading the first two fuel assemblies, following a refueling outage involving complete core off load.

In accordance with 10CFR50.4, a copy of this LER is being forwarded to the NRC Regional Office, NRC Region IV and the Resident Inspector. If you have questions regarding this submittal, please contact Daniel G. Marks, Section Leader, Regulatory Affairs, at (623) 393-6492.

Arizona Public Service Company makes no commitments in this letter. The corrective

- actions described in this LER are not necessary to maintain compliance with - -

regulations.

Sincerely, j

DMS/SAB/DGMWDFH/kg Attachment cc:

B. S. Mallett N. L. Salgado M. B. Fields NRC Region IV Administrator NRC Senior Resident Inspector for PVNGS NRC NRR Project Manager HS17 9-;

Licensee Event Report

Palo Verde

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		Reporting criterion
05000529/LER-2003-001, Regarding Reactor Trip with Loss of Forced Circulation Due to Failed Pressurizer Main Spray Valve	Regarding Reactor Trip with Loss of Forced Circulation Due to Failed Pressurizer Main Spray Valve	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000530/LER-2003-001, Regarding Main Steam Safety Valve as Found Lift Pressures Outside of TS Limits	Regarding Main Steam Safety Valve as Found Lift Pressures Outside of TS Limits	10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000528/LER-2003-001, From Palo Verde, Unit 1 Regarding Pressurizer Safety Valve as Found Lift Pressure Outside of TS Limits	From Palo Verde, Unit 1 Regarding Pressurizer Safety Valve as Found Lift Pressure Outside of TS Limits	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000529/LER-2003-002, Regarding ESF Actuation - Unit 2 Emergency Diesel Generator Actuation	Regarding ESF Actuation - Unit 2 Emergency Diesel Generator Actuation
05000528/LER-2003-002, Manual Reactor Trip Due to Degraded Main Condenser Tube Plug	Manual Reactor Trip Due to Degraded Main Condenser Tube Plug	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000530/LER-2003-002, Re RCS Pressure Boundary Leakage Caused by Degraded Inconel Alloy 600 Components	Re RCS Pressure Boundary Leakage Caused by Degraded Inconel Alloy 600 Components
05000529/LER-2003-003, Corrected Copy of Letter for LER 03-003-00 for Palo Verde, Unit 2	Corrected Copy of Letter for LER 03-003-00 for Palo Verde, Unit 2
05000528/LER-2003-003, Regarding Technical Specification Violation for Failure to Meet Shutdown Cooling Trains Operable Action Statements	Regarding Technical Specification Violation for Failure to Meet Shutdown Cooling Trains Operable Action Statements	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System
05000530/LER-2003-003, Regarding Technical Specification Violation for Failure to Calibrate Nuclear Instrumentation	Regarding Technical Specification Violation for Failure to Calibrate Nuclear Instrumentation	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000529/LER-2003-004, Mode 3 Entry with an Auxiliary Feed Water Pump Inoperable - Technical Specification Violation	Mode 3 Entry with an Auxiliary Feed Water Pump Inoperable - Technical Specification Violation	10 CFR 50.73(a)(2)
05000528/LER-2003-004-04, Regarding Cracks in Contact Block of Main Control Room Handswitches Result in Inoperable Equipment	Regarding Cracks in Contact Block of Main Control Room Handswitches Result in Inoperable Equipment	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 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)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000530/LER-2003-004, Reactor Trip with Loss of Forced Circulation Due to an Electrical Grid Disturbance	Reactor Trip with Loss of Forced Circulation Due to an Electrical Grid Disturbance	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function

05000529/LER-2003-003, Corrected Copy of Letter for LER 03-003-00 for Palo Verde, Unit 2

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Dear Sirs:

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