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I OCFR50.73 hA~
A subsidiary of Pinnacle West Capital Corporation Cliff Eubanks Mail Station 7602 Palo Verde Nuclear Vice President Tel (623) 393-6116 PO Box 52034 Generating Station Nuclear Operations Fax (623) 393-6077 Phoenix, Arizona 85072-2034 102-05396-CE/SAB/DJS January 6, 2006 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit I Docket No. STN 50-528 License No. NPF 41 Licensee Event Report 2005-001-01 Attached please find a supplemental Licensee Event Report (LER) 50-528/2005-001-01 prepared and submitted pursuant to 10 CFR 50.73. This LER reports an event resulting in the actuation of one of the Unit 1 emergency diesel generators, and the subsequent Technical Specification required unit shutdown.
In accordance with 10 CFR 50.4, a copy of this LER is being forwarded to the NRC Region IV Office and the Senior Resident Inspector. Revisions of this report are identified by side bars in the left hand margin. 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, lCE/SAB/DJS/ca A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak 0 Diablo Canyon Palo Verde South Texas Project
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (6-2004)
, the NRC may sfor each block) not conduct or sponsor, and a person Is not required to respond to, the digits/characters frecblk)information collection.
- 3. PAGE Palo Verde Nuclear Generating Station (PVNGS) Unit 1 05000528 1 OF 7
- 4. TITLE Actuation of an Unit I Emergency Diesel Generator (EDG) and Plant Shutdown required by TS
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED MONTH SEUNILRVFCLT NAME DAY YEAR YEAR NUMBER REV MONTH DAY YEAR 1
FACILITY NAME DOCKET NUMBER 02 06 2005 2005 - 001 -
01 01 06(
2006
- 9. OPERATING MODE 11 THIS REPORT IS SUBMITTED PUIRSUANT TO THE REQUIREMENTS OF 10 CFR§: (Checkall that apply)
O 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2X))(C) 0 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(a)(3)(ii)
El 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) o 20.2203(a)(1) 0 20.2203(a)(4)
[I 50.73(aX2)(iiXB)
[l 50.73(a)(2)(viii)(B) o 20.2203(a)(2)(i) 0 50.36(c)(1)(i)(A)
E 50.73(a)(2)(iii)
El 50.73(a)(2)(ix)(A)
- 10. POWER LEVEL 0
20.2203(a)(2)(ii) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iv)(A)
El 50.73(a)(2)(x) o 20.2203(a)(2)(iii)
El 50.36(c)(2)
El 50.73(a)(2)(v)(A)
Dl 73.71(a)(4)
El 20.2203(aX2Xiv)
El 50.46(aX3)(fi)
El 50.73(a)(2)(v)(B) a 73.71(a)(5) 100 E 20.2203(aX2Xv) 0 50.73(aX2)(i)(A)
El 50.73(a)(2)(v)(C)
El OTHER El 20.2203(aX2)(vi)
E 50.73(a)(2)(i)(B)
El 50.73(a)(2)(v)(D)
Specify In Abstract below or in (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of (If more space is required, use additional copies of NIRC Form 366A)
- 9.
PREVIOUS SIMILAR EVENTS
Switchyard and EHV grid events that have affected PVNGS have been reported in LERs 50-528/2004-006-00, 50-529/2004-003-00 and 50-530/2003-004-00. However, these previous events or conditions did not involve the same underlying concern or reason as this event, such as the same root cause, failure, or sequence of events.
There have been no previous similar events in the past three years that had a similar failure mechanism or that should have prevented this event from previously implemented corrective actions.
NRC
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| 05000528/LER-2005-001-01, Re Actuation of an Unit 1 Emergency Diesel Generator (EDG) and Plant Shutdown Required by TS | Re Actuation of an Unit 1 Emergency Diesel Generator (EDG) and Plant Shutdown Required by TS | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000529/LER-2005-001, Regarding Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component | Regarding Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component | 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)(i) 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) | | 05000529/LER-2005-002, Re Tis 3.0.4 Violation; Mode Change Made with One of Two Required LPSI Pumps Inoperable | Re Tis 3.0.4 Violation; Mode Change Made with One of Two Required LPSI Pumps Inoperable | 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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)(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) | | 05000528/LER-2005-002, Regarding Technical Specification Violation: Mode Change with Safety Injection Valve Not in Its Required Position | Regarding Technical Specification Violation: Mode Change with Safety Injection Valve Not in Its Required Position | 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)(i) 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) 10 CFR 50.73(a)(2)(viii)(A) | | 05000529/LER-2005-003, Regarding Two Independent Trains of Auxiliary Feedwater Inoperable | Regarding Two Independent Trains of Auxiliary Feedwater Inoperable | 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) | | 05000528/LER-2005-003, Regarding Calibration Method That Might Have Failed to Provide Reactor Protection During Low Power Operation | Regarding Calibration Method That Might Have Failed to Provide Reactor Protection During Low Power Operation | 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)(x) 10 CFR 50.73(a)(2)(iii) | | 05000529/LER-2005-004, Re Technical Specification Required Shutdown Due to Core Protection Calculators Inoperable | Re Technical Specification Required Shutdown Due to Core Protection Calculators 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)(i)(B), Prohibited by Technical Specifications 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) 10 CFR 50.73(a)(2)(viii)(B) | | 05000528/LER-2005-004, Re Technical Specification Required Reactor Shutdown on EDG B Voltage Regulator Failure | Re Technical Specification Required Reactor Shutdown on EDG B Voltage Regulator Failure | 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), Loss of Safety Function 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 | | 05000529/LER-2005-005, Regarding TS Required Reactor Shutdown - LCO 3.0.3 a Inoperable ECCS, Containment Spray & Refueling Water Tank | Regarding TS Required Reactor Shutdown - LCO 3.0.3 a Inoperable ECCS, Containment Spray & Refueling Water Tank | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000528/LER-2005-005, Re Unplanned Reactor Trip and Engineered Safety Feature Actuation | Re Unplanned Reactor Trip and Engineered Safety Feature Actuation | | | 05000529/LER-2005-006, Regarding Condition Prohibited by Technical Specifications Due to Partial Fouling of B Diesel Generator (EDG) Fuel Oil Strainer | Regarding Condition Prohibited by Technical Specifications Due to Partial Fouling of B Diesel Generator (EDG) Fuel Oil Strainer | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000528/LER-2005-006, Re TS Required Reactor Shutdown on EDG a Failure to Start During Post Maintenance Testing | Re TS Required Reactor Shutdown on EDG a Failure to Start During Post Maintenance Testing | 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)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2) | | 05000528/LER-2005-007, Regarding Potential Loss of Low Pressure Safety Injection (Lps) Due to a Seismic Event | Regarding Potential Loss of Low Pressure Safety Injection (Lps) Due to a Seismic Event | 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) 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000528/LER-2005-008, Re Inverter Failure - Technical Specification Violation | Re Inverter Failure - Technical Specification Violation | 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) 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000528/LER-2005-009, Re Technical Specification Violation for Operation Without Both Reactor Coolant System Loops Operable | Re Technical Specification Violation for Operation Without Both Reactor Coolant System Loops Operable | |
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