LER-2005-005, Re Unplanned Reactor Trip and Engineered Safety Feature Actuation |
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| 5282005005R00 - NRC Website |
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1 OCFR50.73 I
R SA 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) 39346077 Phoenix, Arizona 85072-2034 102-05364-CE/CKS/DGM/DFH October 24, 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 2005-005-00 Attached, please find Licensee Event Report (LER) 50-528/2005-005 which reports an automatic Reactor Protection System (RPS) actuation and an Engineered Safety Feature (ESF) actuation.
In accordance with 1 OCFR50.4, a copy of this LER is being forwarded to the NRC Regional Office, NRC Region IV and the Resident Inspector. 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. The corrective actions described in this LER are not necessary to maintain compliance with regulations.
Sincerely, CE/CKSIDGM/DFH/ca Attachment cc:
B. S. Mallett NRC Region IV Administrator G. G. Wamick NRC Senior Resident Inspector for PVNGS M. B. Fields NRC NRR Project Manager
NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30t2007 (6-2004)
, the NRC may digits/characters for each block) nnotcond~uctorsnponsor, and a person Is not required to respond to, the
- 3. PAGE PALO VERDE NUCLEAR GENERATING STATION UNIT 1 05000528 1 OF 5
- 4. TITLE Unplanned Reactor Trip and Engineered Safety Feature Actuation - Unit 1
- 5. EVENT DATE
- 6. LER NUMBER
- 7. REPORT DATE
- 8. OTHER FACILmES INVOLVED FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR SENUEN L RN MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 08 26 2005 2005 005 00 10 24 2005
- 9. OPERATING MODE
- 11. THIS REPORTIS SUBMITTED PURSUANTTOTHE REQUIREMENTS OF 10CFR§: (Check all that apply) o 20.2201(b) 0 20.2203(aX3)(i) 0 50.73(aX2)(iXC) 0 50.73(aX2Xvii) 2 0 20.2201(d) 0 20.2203(aX3)(ii) 0 50.73(aX2)(iXA) 0 50.73(aX2Xviil)(A) o 20.2203(aXl) 0 20.2203(aX4) 0 50.73(aX2)(IiXB) 0 50.73(aX)(2Xviii)(B) o 20.2203(a)(2Xi) 0 50.36(c)(1Xi)(A) 0 50.73(aX2Xiii) 0 50.73(aX2)(ix)(A)
- 10. POWER LEVEL 0 20.2203(aX2Xii) 0 50.36(c)(1XiiXA) 0 50.73(aX2XivXA) 0 50.73(aX2)(x) 0 20.2203(a)(2Xili) 0 50.36(cX2) 0 50.73(aX2XvXA) 0 73.71(aX4)
O 20.2203(a)(2Xiv) 0 50.46(a)(3Xii) 0 50.73(aX2XvXB) 0 73.71(aX5) 3 0 20.2203(a)(2Xv) 0 50.73(a)(2Xi)(A) 0 50.73(aX2XvXC) 0 OTHER 0 20.2203(aX2Xv!)
0 50.73(a)(2X)(lB) 0 50.73(a)(2XvXD)
Specify In Abstract below I
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)
- 7.
CORRECTIVE ACTIONS
An independent investigation of this event was conducted in accordance with Palo Verde's corrective action program. Listed below are some of the corrective actions from the investigation that were taken or are scheduled in the future.
- Operation's management removed affected personnel from shift duties until preliminary investigation determined extent of performance deficiencies.
- Operation's management coached those personnel removed from shift on personal accountability to ensure compliance with Operations Departments Principles and procedures prior to resumption of shift duties.
- Just-in-time (JIT) training was conducted for the licensed Operator placing the first Main Feed Pump in service including placing the DFWCS into automatic prior to the Unit 1 power ascension above 3%.
- Operation's management will evaluate crew performance and composition to ensure optimal matching of personal strengths necessary to sustain a culture committed to improving performance within the License and Operation's Department Practices and implementing procedures.
- Engineering will modify the DFWCS for all three Units to improve SG level control under single element control at low power.
- Revise Operating Procedures to provide better guidance and human factors when transferring feedwater control from manual to automatic.
8. PREVIOUS SIMILAR EVENTS
No similar condition has been reported in the past three years.
9. ADDITIONAL INFORMATION
None.
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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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