LER-2011-001, Regarding Corrected Copy of APS Cover Letter No. 102-06349-DCM/FJO |
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10 CFR 50.73 AA subsidiary of Pinnacle West Capital Corporation Palo Verde Nuclear Generating Station Thomas N. Weber Department Leader Regulatory Affairs Tel. 623-393-5764 Fax 623-393-5442 102-06427-TNW/FJO October 20, 2011 Mail Station 7636 PO Box 52034 Phoenix, Arizona 85072-2034 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
. Reference:
Arizona Public Service Company (APS) Letter No. 102-06349-DCM/FJO dated April 22, 2011, Licensee Event Report 2011-001-00
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1 and 3 Docket No. STN 50-528 and 50-530 License No. NPF-41 and NPF-74 Corrected Copy of APS Cover Letter No. 102-06349-DCM/FJO APS submitted the referenced letter to the NRC. The train of emergency diesel generator referenced for Unit 1 and Unit 3 in the body of the letter was incorrect.
Enclosed is a corrected copy of the cover letter with a revision bar on the right side of the affected page. Please update your files accordingly.
If you have any questions, please contact Thomas Weber, Department Leader, Regulatory Affairs, at (623) 393-5764.
Arizona Public Service Company makes no commitments in this letter.
Sincerely, C"ladjIaL-TNW/MNW/FJO Enclosure cc:
E. E. Collins Jr.
L. K. Gibson J. R. Hall Tý%ý -rW-MAS WEtlEk NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS (electronic / paper)
NRC NRR Senior Project Manager (electronic / paper)
M. A. Brown NRC Senior Resident Inspector for PVNGS A member of the BTARS (Strategic Teaming and Resource Sharing) Alliance Callaway
ENCLOSURE CORRECTED COVER PAGE TO LETTER 102-06349-DCM/FJO DATED April 22, 2011 LICENSEE EVENT REPORT 2011-001-00
10 CFR 50.73
& A' A subsidiary of Pinnacle West Capital Corporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Senior Vice President Tel. 623-393-5403 P.O. Box 52034 Generating Station Nuclear Regulatory and Oversight Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06349-DCM/FJO April 22, 2011 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1 and 3 Docket No. STN 50-528 and 50-530 License No. NPF-41 and NPF-74 Licensee Event Report 2011-001-00 Enclosed please find Licensee Event Report (LER) 50-528/2011-001-00 that has been prepared and submitted pursuant to 10 CFR 50.73. This LER reports an automatic actuation of the circuitry that starts the Unit 1 Train 'B' and Unit 3 Train 'A' emergency diesel generators due to an undervoltage condition on their respective 4.16 kV safety buses.
In accordance with 10 CFR 50.4, copies of this LER are being forwarded to the Nuclear Regulatory Commission (NRC) Regional Office, NRC Region IV and the Senior Resident Inspector. If you have questions regarding this submittal, please contact Marianne Webb, Section Leader, Regulatory Affairs, at (623) 393-5730.
Arizona Public Service Company makes no commitments in this letter.
Sincerely, [original signed by Dwight Mims]
DCM/TNW/MNW/FJO/gat Enclosure cc:
E. E. Collins Jr.
NRC Region IV Regional Administrator L. K. Gibson NRC NRR Project Manager for PVNGS (electronic / paper)
J. R. Hall NRC NRR Senior Project Manager (electronic / paper)
M. A. Brown NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway - Comanche Peak - Diablo Canyon
- Palo Verde ° San Onofre ° South Texas - Wolf Creek
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| 05000528/LER-2011-001, Regarding Corrected Copy of APS Cover Letter No. 102-06349-DCM/FJO | Regarding Corrected Copy of APS Cover Letter No. 102-06349-DCM/FJO | | | 05000529/LER-2011-001, For Palo Verde Unit 2, Irradiated Fuel Movement with Misaligned Control Room Essential Filtration System | For Palo Verde Unit 2, Irradiated Fuel Movement with Misaligned Control Room Essential Filtration System | 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-2011-001, For Palo Verde, Unit 3, Regarding Reactor Trip Due to Failed Open Main Feedwater Pump a Minimum Flow Recirculation Valve | For Palo Verde, Unit 3, Regarding Reactor Trip Due to Failed Open Main Feedwater Pump a Minimum Flow Recirculation Valve | 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) | | 05000529/LER-2011-002-01, Inoperable Steam Generator Low Pressure Reactor Trip and Main Steam Isolation Signal Channels | Inoperable Steam Generator Low Pressure Reactor Trip and Main Steam Isolation Signal Channels | 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) | | 05000528/LER-2011-002, For Palo Verde, Unit 1, Regarding Nonconforming Condition Renders the Qualified Safety Parameter Display System Inoperable | For Palo Verde, Unit 1, Regarding Nonconforming Condition Renders the Qualified Safety Parameter Display System Inoperable | 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) | | 05000529/LER-2011-002, Regarding Inoperable Steam Generator Low Pressure Reactor Trip and Main Steam Isolation Signal Channels | Regarding Inoperable Steam Generator Low Pressure Reactor Trip and Main Steam Isolation Signal Channels | 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) | | 05000528/LER-2011-003, For Palo Verde, Unit 1, Regarding Control Room Essential Filtration Misalignment Resulting in Condition Prohibited by Technical Specifications | For Palo Verde, Unit 1, Regarding Control Room Essential Filtration Misalignment Resulting in Condition Prohibited by Technical Specifications | 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)(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) | | 05000528/LER-2011-004, Regarding Reactor Trip Due to Reactor Protection System Actuation Which Resulted from a Dropped CEA | Regarding Reactor Trip Due to Reactor Protection System Actuation Which Resulted from a Dropped CEA | 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) | | 05000528/LER-2011-005, For Palo Verde, Unit 1, Regarding Manual Reactor Trip Due to Slipped Control Elemental Assemblies | For Palo Verde, Unit 1, Regarding Manual Reactor Trip Due to Slipped Control Elemental Assemblies | 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) |
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