LER-2008-001, TS Required Shutdown Due to EDG Repair Beyond Allowed Outage Time |
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10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown |
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| 3622008001R00 - NRC Website |
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SOUTHERN CALIFORNIA EDISON" An EDISON INTERNATIONAL@ Company October 27, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
Docket No. 50-362 Licensee Event Report No. 2008-001 San Onofre Nuclear Generating Station, Unit 3
Dear Sir or Madam:
This submittal provides Licensee Event Report (LER) 2008-001, in accordance with 10 CFR 50.73(a)(2)(i)(A) to report the completion of a Technical Specification required shutdown. This shutdown was required to complete repair of the Emergency Diesel Generator, train "B", beyond the Allowed Outage Time.
Sincerely, Albert R. Hochevar Station Manager Unit 3 LER No. 2008-001 cc:
E. E. Collins, NRC Regional Administrator, Region IV G. G. Warnick, NRC Senior Resident Inspector, San Onofre Units 2 & 3 P.O. Box 128 San Clemente, CA 92674-0128
Abstract
On 9/1/08, at about 1035 PDT, with Unit 3 near full power, plant operators manually initiated a plant shutdown to complete repairs on Emergency Diesel Generator (EDG) 3G003. A condition identified while performing testing following the replacement of the generator, required the EDG to be inoperable longer than allowed by Technical Specification 3.8.1 (14 days). At 1403 PDT, SCE reported initiation of the shutdown on 9/1/08 (NRC Log No. 44456) under 10 CFR 50.72(b)(2)(i). Operators tripped the reactor on 9/1/08 at 14:47 PDT. SCE is submitting this report in accordance with 10 CFR 50.73(a)(2)(i)(A).
The Allowed Outage Time (AOT) began on 8/19/08 as planned maintenance that included replacement of bearings on Diesel fuel racks and an inspection of the generator. The inspection revealed cracks in the shorting ring, requiring replacement of the generator. Post-maintenance testing revealed anomalous readings that could not be resolved during the AOT. Subsequently, SCE determined that the readings were due to an improper fit of a newly replaced bearing, causing momentary binding of a fuel rack. The bearing was replaced, the Surveillance Requirements met and the EDG was returned to Operable status. The reactor returned to Mode 1 on 9/11/08 at about 22:22 PDT.
The shutdown was a normal, uncomplicated plant shutdown. Therefore, the significance of this event was minimal.
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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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