05000528/LER-2004-009, Supplemental Report to Licensee Event Report 2004-009-00

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Supplemental Report to Licensee Event Report 2004-009-00
Person / Time
ML050140142
Site:	Palo Verde
Issue date:	01/07/2005
From:	Danni Smith Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05198-DMS LER 04-009-00
Download: ML050140142 (1)
v • d • e

LER-2004-009, Supplemental Report to Licensee Event Report 2004-009-00

Event date:
Report date:
5282004009R00 - NRC Website
v • d • e

text

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sbshvidiary ofPinnal"e l1i'st Capital Cotr7aration Palo Verde Nuclear 1 OCFR50.73 Generating Station David M. Smith Tel.

623-393-6116 Mail Station 7602 Plant Manager Fax.

623-393-6077 P.O. Box 52034 Nuclear Production e-mail: DSMITH10@apsc.com Phoenix, AZ 85072-2034 102-05198-DMS January 7, 2005 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 References: 1. APS Letter-# 192-01154-DMS/RAS, David M. Smith (APS) to.NRC-Document Control Desk, Licensee Event Report 2004-009-00, dated September 28, 2004.

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket No. STN 50-528, 50-529, 50-530 License No. NPF-41, NPF 51, NPF 74 Supplemental Report to Licensee Event Report 2004-009-00 Licensee Event Report (LER) 50-528/2004-009-00 was prepared and submitted pursuant to 10 CFR 50.73 (Reference 1). The LER reported a condition in Units 1, 2, and 3 where voids in Emergency Core Cooling System containment sump piping may have prevented the fulfillment of the system safety function to remove residual heat and mitigate the consequences of a Loss of Coolant Accident. The LER stated a Supplemental Report was expected to be submitted on December 30, 2004. APS is still evaluating additional testing data and now expects to submit the Supplemental Report on March 31, 2005.

In accordance with 10 CFR 50.4, a copy of this letter is being forwarded to the NRC Region IV Office and the Senior 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.

Sincerely, DMS/djs cc:

B. S. Mallet, Region IV Administrator N. L. Salgado, Sr. Resident Inspector M. B. Fields, PVNGS Project Manager

Licensee Event Report

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		Reporting criterion
05000529/LER-2004-001, Regarding Steam Generator Tube Leak	Regarding Steam Generator Tube Leak	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)(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
05000530/LER-2004-001, Re RCS Pressure Boundary Leakage Caused by Degraded Alloy 600 Component	Re RCS Pressure Boundary Leakage Caused by Degraded Alloy 600 Component
05000528/LER-2004-001, Regarding Reactor Shutdown Due to Reactor Coolant System Pressure Boundary Leakage	Regarding Reactor Shutdown Due to Reactor Coolant System Pressure Boundary Leakage
05000530/LER-2004-002, Regarding an Automatic Reactor Trip on Low DNBR Following a Main Turbine Control System Malfunction	Regarding an Automatic Reactor Trip on Low DNBR Following a Main Turbine Control System Malfunction
05000530/LER-2004-002-01, 1 for Palo Verde, Unit 3 Regarding Main Turbine Control System Malfunction Results in Automatic Reactor Trip on Low DNBR	1 for Palo Verde, Unit 3 Regarding Main Turbine Control System Malfunction Results in Automatic Reactor Trip on Low DNBR	10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)
05000529/LER-2004-002, On 07/14/2004 Reactor Tripped on Low Departure from Nucleate Boiling Ratio (DNBR)	On 07/14/2004 Reactor Tripped on Low Departure from Nucleate Boiling Ratio (DNBR)	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)(vi)(A) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000528/LER-2004-002, Technical Specification Violation - Exceeded 20% RTP with LCO Not Met	Technical Specification Violation - Exceeded 20% RTP with LCO Not Met
05000529/LER-2004-003, Regarding Actuation of Plant Emergency Diesel Generators	Regarding Actuation of Plant Emergency Diesel Generators	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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000528/LER-2004-003, Unit I, Regarding Manual Reactor Trip - Slipped Control Element Assembly	Unit I, Regarding Manual Reactor Trip - Slipped Control Element Assembly	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000528/LER-2004-004, Re Missed Surveillance Requirement for Temperature Detector Calibration	Re Missed Surveillance Requirement for Temperature Detector Calibration
05000528/LER-2004-005, Re Missed Surveillance Tests on Shutdown Cooling Valve RCS Pressure Interlocks	Re Missed Surveillance Tests on Shutdown Cooling Valve RCS Pressure Interlocks	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)(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) 10 CFR 50.73(a)(2)(viii)(A)
05000528/LER-2004-006, Regarding a Loss of Offsite Power (LOOP) and the Subsequent Reactor Trip	Regarding a Loss of Offsite Power (LOOP) and the Subsequent Reactor Trip
05000528/LER-2004-007, Regarding Exceeding the Maximum Power Level Specified in Operating License Condition 2.C(1)	Regarding Exceeding the Maximum Power Level Specified in Operating License Condition 2.C(1)
05000528/LER-2004-008, Regarding Improper Contact Configuration on Containment Isolation Valve	Regarding Improper Contact Configuration on Containment Isolation Valve
05000528/LER-2004-009, Supplemental Report to Licensee Event Report 2004-009-00	Supplemental Report to Licensee Event Report 2004-009-00
05000528/LER-2004-011, Re Missed Surveillance Requirements for Containment Lvs Test/Drain Valves	Re Missed Surveillance Requirements for Containment Lvs Test/Drain Valves	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)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

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