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1 OCFR50.73 LAMP Palo Verde Nudear Generating Station A subsidiary of Pinnacle West Capital Corporation David M. Smith Plant Manager Nuclear Production Tel: 623-393-6116 Faxz 623-393-6077 e-mail: DSMlTH10@apsccom Mail Station 7602 PO Box 52034 Phoenix. Arizona 85072-2034 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 102-05299-DMS/CKS/DJS June 20, 2005
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 2 Docket No. STN 50-529 License No. NPF-51 Licensee Event Report 2005-001-00 Attached please find Licensee Event Report (LER) 50-529/2005-001-00 that has been prepared and submitted pursuant to 1 OCFR50.73. This LER reports the discovery and corrective actions taken as a result of finding two axial indications in the reactor vessel head vent penetration during the unit's 12t refueling outage. While performing reactor vessel head vent eddy current examinations and data evaluation, two (2) axial indications were confirmed on the vent ID surface, indicating potential primary water stress corrosion cracking (PWSCC) and degradation of the vent penetration. The axial indications were repaired prior to Unit 2 resuming power operation.
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.
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.
Sincerely, DMS/CKS/DJS/ca Attachment cc:
B. S. Mallett M. B. Fields G. G. Wamick NRC Region IV Regional Administrator NRC NRR Project Manager - (send electronic and paper)
NRC Senior Resident Inspector for PVNGS LA,t(J-N
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APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 Estumated burden per response to comply With this mandatory collection NRC004 OR 36 U..NCERR ULTRCOMSIN request: 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Reported lessons learned are Incorporated Into the licensing (LI2004)
EOprocess and fed back to Industry. Send comments regarding burden estimate to LICENSEE EVENT REPORT (LER) the Records and FOIAJPrivacy Service Branch (T-5 F52), U.S. Nuclear (See reverse for required number of Regulatory Commission, Washington. DC 20555-0001, or by Internet e-mail to digltslcharacters for each block)
Infocollects@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104). Office of Management and Budget. Washington, DC 20503. If a means used to Impose an Information
- 3. PAGE Palo Verde Nuclear Generating Station (PVNGS) Unit 2 05000529 1 OF 6
- 4. TITLE REACTOR HEAD VENT AXIAL INDICATIONS CAUSED BY DEGRADED ALLOY 600 COMPONENT
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILITIES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SEQUENTIAL REV MONTH DAY YEAR 05000 INUMBER NO.
50 FACILITY NAME DOCKET NUMBER 04 23 2005 2005 - 001 -
00 06 20 2005 05000
- 9. OPERATING MODE II. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR§: (Check all that apply) o 20.2201(b) 0 20.2203(a)(3)(i) 0 50.73(a)(2)(i)(C) 0 50.73(a)(2Xvi) 6 - Defueled 0 20.2201(d) 0 20.2203(aX3)(ii) xx 50.73(a)(2)(iiXA)
El 50.73(a)(2Xvviii)(A) o 20.2203(a)(1)
El 20.2203(a)(4)
El 50.73(a)(2)(ii)(B)
El 50.73(a)(2xviii)(B) 0I 20.2203(a)(2Xi) 0 50.36(c)(1)(i)(A) 0 50.73(a)(2)(iii) 0 50.73(a)(2Xix)(A)
- 10. POWER LEVEL 0 20.2203(aX2XIi)
El 50.36(c)(1)(iiXA) 0 50.73(a)(2)(ivXA) 0 50.73(a)(2Xx) o 20.2203(a)(2XIii) a 50.36(c)(2) 0 50.73(a)(2)(v)(A)
El 73.71(a)(4) o 20.2203(a)(2)(iv)
El 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(B)
El 73.71(a)(5) 000 0 20.2203(a)(2)(v)
Dl 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(C) 0 OTHER El 20.2203(aX2)(vi) 0 50.73(aX2)(i)(B) 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 (If more space is required, use additional copies of NRC Form 366A) 4DD: I B,,Mv
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i DETAIL F (C 4 SECT 1
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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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