LER-2008-001, Regarding Valid Actuation of Emergency Feedwater System Following Main Feedwater Pump Trip |
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10 CFR 50.73(a)(2)(iv)(A), System Actuation |
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| 3612008001R00 - NRC Website |
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JSOUTHERN CALIFORNIA EDISON An EDISON INTERNATIONAL Company Ross T. Ridenoure VP and Site Manager San Onofre Nuclear Generating Station February 22, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
Docket No. 50-361 Licensee Event Report No. 2008-001 San Onofre Nuclear Generating Station, Unit 2
Dear Sir or Madam:
In compliance with 1 OCFR50.73(a)(2)(iv)(A), this submittal provides Licensee Event Report (LER) 2008-001 to report an event that resulted in valid actuation of the emergency feedwater system. Neither the health nor the safety of plant personnel or the public was affected by this occurrence.
If you require any additional information, please contact me.
Sincerely, Unit 2 LER No. 2008-001 cc:
E. E. Collins, NRC Regional Administrator, Region IV C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 & 3 Mail Drop D45 P.O. Box 128 San Clemente, CA 92672 949-368-6255 PAX 86255 Fax: 949-368-6183 Ross.Ridenoure@sce.com
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Abstract
On 1/23/08, at about 1415 PST, with SONGS Unit 2 in Mode 1 at about 95 percent power, one of two main feedwater (MFW) [SJ] pumps tripped on low oil pressure. Control room operators manually actuated the emergency feedwater system (AFW) [BA] in accordance with plant procedures. The AFW system responded successfully. Control room operators reduced reactor power level to about 65 percent which can be sustained with one normal feedwater pump in operation.
The AFW manual actuation by plant operators was in response to the MFW pump trip. The MFW pump trip was due to overadjustment of the pump lubricating oil pressure regulator. Maintenance workers used the pump overhaul procedure that did not provide sufficient detail to adjust the oil pressure regulator while the pump is on-line.
The oil pressure regulator was correctly adjusted and the Unit was returned to power. SCE is completing a cause evaluation which may identify additional corrective actions.
All systems responded as designed and Control Room personnel acted timely and correctly. Neither the health nor the safety of plant personnel or the public were affected by this occurrence.
No valid actuation of the AFW due to inappropriate procedures has occurred over the last 3 years.
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| | | Reporting criterion |
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| 05000362/LER-2008-001, TS Required Shutdown Due to EDG Repair Beyond Allowed Outage Time | TS Required Shutdown Due to EDG Repair Beyond Allowed Outage Time | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | | 05000361/LER-2008-001, Regarding Valid Actuation of Emergency Feedwater System Following Main Feedwater Pump Trip | Regarding Valid Actuation of Emergency Feedwater System Following Main Feedwater Pump Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000362/LER-2008-002, For San Onofre, Unit 3, Regarding Loose Fuse Results in Inoperable Auxiliary Feedwater Pump and TS Violation | For San Onofre, Unit 3, Regarding Loose Fuse Results in Inoperable Auxiliary Feedwater Pump and TS Violation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000361/LER-2008-002, & 08-003-00 for San Onofre Nuclear Generating Station Unit 2 Disturbance on the Pacific DC Intertie Cause Offsite Power Frequency to Dip Below Operability Limits | & 08-003-00 for San Onofre Nuclear Generating Station Unit 2 Disturbance on the Pacific DC Intertie Cause Offsite Power Frequency to Dip Below Operability Limits | 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)(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
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000362/LER-2008-003, For San Onofre, Regarding Missed TS Completion Time Results in TS Violation | For San Onofre, Regarding Missed TS Completion Time Results in TS Violation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000361/LER-2008-004, Regarding Malfunctioning Stator Water Cooling System Check Valve Causes Reactor Trip | Regarding Malfunctioning Stator Water Cooling System Check Valve Causes Reactor Trip | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | | 05000361/LER-2008-005, Regarding Missed Surveillance and Plant Mode Change Causes TS Violation | Regarding Missed Surveillance and Plant Mode Change Causes TS Violation | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000361/LER-2008-006, Regarding Loose Connection Bolting Results in Inoperable Battery and TS Violation | Regarding Loose Connection Bolting Results in Inoperable Battery and TS Violation | 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)(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)(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)(viii)(A) | | 05000361/LER-2008-007, Failure to Comply with TS Surveillance Requirement Completion Time | Failure to Comply with TS Surveillance Requirement Completion Time | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000361/LER-2008-008, Regarding Missed Technical Specification Surveillance Requirement on Spare Station Battery B00X | Regarding Missed Technical Specification Surveillance Requirement on Spare Station Battery B00X | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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