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10 CFR 50.73 LAMS A subsidiary of Pinnacle West Capitol Corporation Palo Verde Nuclear Generating Station Cliff Eubanks Vice President Nuclear Operations Tel (623) 393-6116 Fax (623) 393-6077 Mail Station 7602 PO Box 52034 Phoenix, Arizona 85072-2034 102-05354-CE/CKS/DLK October 7, 2005 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 2005-004-00 Attached please find Licensee Event Report (LER) 50-528/2005-004-00 prepared and submitted pursuant to 10 CFR 50.73. This LER reports a shutdown required by Technical Specifications based on the inability to return MB" Emergency Diesel Generator to operable status following a failed routine surveillance test within the required action completion time.
In accordance with 10 CFR 50.73(d), copies of this LER are being forwarded to the NRC Regional Office, NRC Region IV 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.
The corrective actions described in this LER are not necessary to maintain compliance with regulations. Arizona Public Service Company makes no commitments in this letter.
Sincerely, CE/CKS/DLK/ca Attachment cc:
B. S. Mallett M. B. Fields G. G. Warnick NRC Region IV Regional Administrator NRC NRR Project Manager - (send electronic and paper)
NRC Senior Resident Inspector for PVNGS
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 0613012007
~6-2004) the NRC may not conduct or sponsor, and a person Is not required to respond to. the digits/characters for each block)
Information collection.
- 3. PAGE Palo Verde Nuclear Generating Station Unit 1 05000528 1 OF 4
- 4. TITLE Technical Specification Required Reactor Shutdown on EDG "B" Voltage Regulator Failure
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED SEUETIL EVFACiUIwY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NSEUENTIAL REV MONTH DAY YEAR None 05000 j
FACILITY NAME DOCKET NUMBER 08 12 2005 2005 - 004 -
00 10 07 2005 None 05000
- 9. OPERATING MODE 1
i. THIS REPORT IS SUBMITTED PURSUANTTO THE REQUIREMENTS OF 10 CFR§: (Check allthat apply) o 20.2201(b)
El 20.2203(a)(3)(i)
El 50.73(a)(2)(i)(C) 0 50.73(a)(2Xvii) 1 0 20.2201(d)
E: 20.2203(aX3)(ii)
El 50.73(a)(2)(ii)(A)
E] 50.73(a)(2Xviii)(A) ol 20.2203(a)(1)
E3 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2&viii)(B)
El 20.2203(a)(2X))
El 50.36(c)(1)(i)(A)
El 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)(iiXA)
El 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(aX2)(v)(A)
El 73.71(a)(4) 0 20.2203(a)(2)(iv)
E 50.46(aX3)(ii)
El 50.73(aX2)(v)(B)
E 73.71(a)(5) 94 Cl 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A)
El 50.73(aX2)(v)(C) a OTHER o 20.2203(a)(2)(vi) 0 50.73(a)(2)(i)(B)
[I 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 NRC Form 366A)
The event did not result in a transient more severe than those analyzed in the updated Final Safety Evaluation Report Chapters 6 and 15. The event did not have any nuclear safety consequences or personnel safety impact.
The condition would not have prevented the fulfillment of any safety function and did not result in a safety system functional failure as defined by 10 CFR 50.73(a)(2)(v).
- 6.
CAUSE OF THE EVENT
The cause of the event was the inability to return EDG "B" to operable status within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> required action completion time allowed by LCO 3.8.1 condition "B."
The root cause of the EDG "B" voltage anomalies was a failed Automatic Voltage Regulator (AVR) (EIIS code: EK, DG, RG). The AVR manufacturer is NEI Peebles/Portec, model number 72-08300-100.
The engineering action plan to troubleshoot the voltage anomalies attempted to first rule out possible causes not associated with the AVR in part because replacement of the AVR would require post maintenance load rejection surveillance testing in accordance with Technical Specification Surveillance Requirement (SR) 3.8.1.9. Performance of this surveillance is prohibited in Modes 1 through 4.
- 7.
CORRECTIVE ACTIONS
On August 12, 2005 the reactor was manually shutdown. The AVR on EDG "B" was replaced and all retests were completed satisfactorily. On August 14, 2005, at 1232, EDG "B" was returned to operable status.
A significant investigation into the EDG "B" voltage anomalies is currently in progress. If results from the significant investigation identify substantial information that would change the reader's perception of the event or corrective actions described in this LER, a supplemental LER will be submitted.
- 8.
PREVIOUS SIMILAR EVENTS
In the past three years, Palo Verde reported reactor shutdowns required by Technical Specifications but none associated with the same root cause.
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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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