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e, 10 CFR 50.73 A subsidiary of Pinnacle West Capital Corporation Palo Verde Nudear 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 102-05373-CE/CKS/DJS November 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 1 Docket No. STN 50-528 License No. NPF 41 Licensee Event Report 2005-006-00 Attached please find Licensee Event Report (LER) 50-528/2005-006-00 prepared and submitted pursuant to 10 CFR 50.73. This LER reports a shutdown required by Technical Specifications based on the inability to return "A" Emergency Diesel Generator to operable status following a failed routine surveillance test within the TS action completion time. This report also discusses the failure to complete the required LER within sixty (60) days of the event which occurred on March 18, 2005.
In accordance with 10 CFR 50.4, 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.
CE/CKS/DJS/ca Attachment cc:
B. S. Mallett M. B. Fields G. G. Wamick Sincerely, NRC Region IV Regional Administrator NRC NRR Project Manager - (send electronic and paper)
NRC Senior Resident Inspector for PVNGS
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06130/2007 (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 5
- 4. TITLE TS Required Reactor Shutdown on EDG "A" Failure to Start During Post Maintenance Testing
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED RVFACLiTY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER REV MONTH DAY YEAR 05000 FACILITY NAME DOCKET NUMBER 03 18 2005 2005 - 006 -
00 11 07 2005 05000
- 9. OPERATING MODE 11.THIS REPORT IS SUBMITTED PURSUANTTO THE REQUIREMENTS OF 10 CFR§: (Check all hat apply) 0 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(aX2)(i)(C) a 50.73(a)(2)(vii) 1 0 20.2201(d) 0 20.2203(a)(3)(ii) 0 50.73(a)(2)(ii)(A)
E 50.73(a)(2)(viiXA)
O 20.2203(a)(1)
El 20.2203(a)(4) 0 50.73(a)(2)(iI)(B) 0 50.73(a)(2)(viiiXB) 0o 20.2203(a)(2)(i)
El 50.36(c)(IXiXA) 0 50.73(a)(2Xiii) 0 50.73(a)(2XIx)(A)
- 10. POWER LEVEL El 20.2203(a)(2)(ii)
E0 50.36(c)(1)(ii)(A)
El 50.73(a)(2&iv)(A) 0 50.73(a)(2Xx)
O] 20.2203(a)(2)(iii) 0 50.36(c)(2) 0 50.73(a)(2)(v)(A) 0 73.71(a)(4) o 20.2203(a)(2)(iv) 0 50.46(a)(3X1I) l 50.73(a)(2)(v)(B) 0 73.71(a)(5) 100 0
20.2203(a)(2)(v) 10 50.73(a)(2Xi)(A) 0 50.73(a)(2)(v)(C) 0 OTHER o 20.2203(a)(2)(vi) 0 50.73(a)(2XIXB) 0 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 NRC Form 366A)
SIGNIFICANT Maintenance Rule Functional Failure (MRFF)" Condition Reports/Disposition Request (CRDR) # 2782680 would be returned to the CRDR Review Committee for reclassification to "SIGNIFICANT" when the condition becomes reportable. A review of CRDR 2782680 determined that it was not reclassified until 04/01/2005 when it was determined to be (solely) a Maintenance Rule Functional Failure (MRFF) (SIGNIFICANT EQUIPMENT ROOT CAUSE OF FAILURE ANALYSIS).
CRDR 2783081 was written to document the reports required for the Unit 1 normal shutdown. A review of CRDR 2783081 determined that it was only classified as REVIEW -CLOSED because the shutdown had no other complications, further supporting the "mental lapse" theory.
- 7.
CORRECTIVE ACTIONS
On March 18, 2005 the reactor was manually shutdown. The governor on EDG "A" was replaced and all retests were completed satisfactorily. The Unit was started and synchronized to the grid on March 21, 2005.
A significant investigation into the EDG "A" governor failure has been completed.
The late LER submittal was a cognitive error. All members of the Regulatory Affairs group were counseled regarding this omission to report the completion of a TS required plant shutdown.
- 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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