LER-2008-005, Regarding Missed Surveillance and Plant Mode Change Causes TS Violation |
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10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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| 3612008005R00 - NRC Website |
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FSOUTHERN CALIFORNIA 1 EDISON An EDISON INTERNATIONAL Company July 30, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001
Subject:
Docket No. 50-361 Licensee Event Report No. 2008-005 San Onofre Nuclear Generating Station, Unit 2
Dear Sir or Madam:
In compliance with 10CFR50.73(a)(2)(i)(B), this submittal provides Licensee Event Report (LER) 2008-005 to report a missed surveillance preceding a Mode change.
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, Albert R. Hochevar Station Manager Unit 2 LER No. 2008-005 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 KiEQZ.
Abstract
On 6/9/08 at about 1314 PDT, San Onofre Nuclear Generating Station, Unit 2 entered Mode 2 from Mode 3 in accordance with startup procedures. At about 1443 PDT, the Control Room Supervisor (CRS) recognized that the Control Element Assembly (CEA) [AA] Alignment Surveillance Requirements (SR) 3.1.5.1 and SR 3.1.5.2 had not been completed prior to Mode change. (Technical Specification (TS) 3.1.5 is applicable in Modes 2 and 1, but not in Mode 3 or lower). Because SR 3.0.4 prevents entry into Modes without completion of all applicable SRs, SCE is reporting this occurrence in accordance with 1 OCFR50.73(a)(2)(i)(B).
Operators completed the surveillances with satisfactory results. Consequently, there was no safety significance to this occurrence.
This event was caused by (1) a lack of detail in the applicable procedure and (2) lack of oversight by the Control Room Supervisor (Utility, Licensed). SCE has coached the Operators (Utility, Licensed) involved and will revise the affected procedure.
LER 3-2006-005, dated 1/26/07, reported an instance of exceeding 20 percent power without all required SRs completed. That event resulted from a boron dilution error during startup. LER 2-2007-002, dated 8/17/07, reported a missed TS SR required with the plant entered Mode 3 following a failure of the instrument air system and consequential plant trip.
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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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