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{
    "query_string": "[[Category:Licensee Event Report]] [[Site::Docket Number]] [[LER year::2006]]",
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	Title	Reporting criterion
05000306/LER-2006-001		10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000315/LER-2006-001	Plant Shutdown Required by Technical Specification Action 3.6.5.B.1
05000315/LER-2006-002	Failure to Comply with Technical Specification Requirement 3.6.13, Divider Barrier Integrity	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000315/LER-2006-003	Failure to Comply with Technical Specification 3.3.6, Containment Purge Supply and Exhaust System Isolation	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000316/LER-2006-001	Failure to Comply with Technical Specification 3.6.2, Containment Air Locks	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000316/LER-2006-002		10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000316/LER-2006-004	Failure to comply with Technical Specification 3.8.2, AC Sources - Shutdown, LCO 3.8.2.b	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
05000316/LER-2006-005	Failure to Comply with Technical Specification Surveillance Requirement 3.6.1.1	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000335/LER-2006-003	Unanalyzed Condition for Diesel Generators and Degraded Voltage Relaying	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000336/LER-2006-001		10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
05000336/LER-2006-002	Manual Reactor Trip Due To Trip Of Both Feed Pumps Following A Loss Of Instrument Air	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000336/LER-2006-003		10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000336/LER-2006-004	Failure to Enter the Technical Specification Action Statement for Inoperable Reactor Protection System Trips	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000336/LER-2006-005	Inadvertent Actuation of 'A' Motor Driven Auxiliary Feedwater Pump	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000346/LER-2006-003	Degraded Condenser Pressure Due to Failed Drain Line Results in Manual Reactor Trip	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000348/LER-2006-002	Main Steam Isolation Valve Failure to Close	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000352/LER-2006-001	Loss Of One Offsite Circuit Due To Invalid Actuation Of Fire Suppression System	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000353/LER-2006-001	HPCI Ramp Generator Signal Converter Failure	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident 10 CFR 50.73(a)(2)(v), Loss of Safety Function
05000362/LER-2006-002	Unit 3 Shutdown to Inspect Safety Injection Tank Spiral Wound Gaskets
05000362/LER-2006-003	Reactor Coolant System Pressure Boundary Leak Caused by Incomplete Compression of a Mechanical Nozzle Seal Assembly Grafoil Seal.	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000362/LER-2006-004	Station ManagerEDISON® San Onofre An EDISON INTERNATIONAL@ Company November 22, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001 Subject:DDocket No. 50-362 Licensee Event Report No. 2006-004 San Onofre Nuclear Generating Station, Unit 3 Dear Sir or Madam: This submittal provides Licensee Event Report (LER) 2006-604, which describes an occurrence of an inoperable breaker causing a charging pump to be inoperable longer than allowed by Technical Specifications. This event did not affect the health and safety of either plant personnel or the public. If you require any additional information, please contact me. Sincerely, Unit 3 LER No. 2006-004 cc:DB. S. Mallett, NRC Regional Administrator, Region IV C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 & 3 P.O. Box 128 San Clemente, CA 92674-0128 949-368-9263/PAX 89263 Fax 949-368-6183 breigdp@songs.sce.com ) ARC FORM 366 U.S. NUCLEAR REGULATORY APPROVED BY OMB: NO. 3150-0104 EXPIRES: 06/30/2007 (7-2001) COMMISSION Estimated burden per response to comply with this mandatory information collection request: 50 hours. Reported lessons learned are incorporated into the licensing process and fed back to industry. Send comments regarding burden estimate to the Records Management Branch (T-6 E6), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by internet e-mail to bjs@nrc.gov, andLICENSEE EVENT REPORT (LER) to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202 (3150-0104), Office of (See reverse for required number of Management and Budget, Washington, DC 20503. If a means used to impose information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection. digits/characters for each block) 1. FACILITY NAME 2. DOCKET NUMBER 3. PAGE San Onofre Nuclear Generating Station (SONGS) Unit 3 05000362 1 OF 4 4. TITLE Inoperable breaker causes train "A" charging pump to be inoperable for longer than allowed by Technical Specifications	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000362/LER-2006-005	Dilution error results in exceeding 20 percent power prior to completion of required surveillances	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000362/LER-2006-006	One train of Component Cooling Water considered inoperable for longer than allowed by Technical Specification 3.7.7 due to gas entrainment.	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000368/LER-2006-001	Completion of a Plant Shutdown Required by Technical Specifications Due to Loss of Motive Power to Certain Containment Isolation Valves as a Result of a Phase to Ground Short Circuit in a Motor Control Cubicle	10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown
05000369/LER-2006-001	Ice Condenser and Floor Cooling System Containment Isolation Valve inoperable longer than allowed by Technical Specification 3.6.3.
05000387/LER-2006-002	DMissed Technical Specification surveillance requirement	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000388/LER-2006-002	Missed Technical Specification LCO 3.8.1 Entry for Unit 2 During Unit 1 ESS Bus Testing	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000389/LER-2006-003	Missed Eddy Current Indication from SL2 - 1 5 Inspection	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000389/LER-2006-004		10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000395/LER-2006-004	Turbine Trip Due To High Steam Generator Level P-14 05000	10 CFR 50.73(a)(2)(iv), System Actuation
05000413/LER-2006-001		10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000413/LER-2006-002	Safe Shutdown Potentially Challenged by an External Flooding Event and Inadequate Design and Configuration Control	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000413/LER-2006-003	Technical Specification Violations Associated with H drogen Ignition System	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000423/LER-2006-001	Loss Of Safety Function Of The Control Room Emergency Ventilation System	10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident
05000440/LER-2006-001	Incorrect Wiring in the Remote Shutdown Panel Results in a Fire Protection Program Violation
05000440/LER-2006-002	Scaffold Built in the Containment Pool Swell Region	10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition
05000440/LER-2006-004	OSCILLATION POWER RANGE MONITORS (OPRMs) INOPERABLE	10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000440/LER-2006-005	Decreasing Instrument Air Pressure Results in Manual Reactor Protection System Actuation	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000440/LER-2006-006	Primary Containment Airlock Door Inoperability Results in Operation Prohibited by Technical Specifications	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000443/LER-2006-002	Noncompliance with the Requirements of Technical Specification 6.8.1.2.a
05000443/LER-2006-004	Technical Specification Violation Due to Inoperable Battery Charger	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000443/LER-2006-005	Technical Specification Violation with Inoperable Main Steam Isolation Valve	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
05000454/LER-2006-001	Technical Specification Required Action Completion Time Exceeded for Inoperable Containment Isolation Valves Due to Untimely Operability Determination
05000456/LER-2006-001	Unit 1 Reactor Coolant System Pressure Boundary Leakage Due To Inter-Granular Stress Corrosion Cracking of a Pressurizer Heater Sleeve	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded
05000456/LER-2006-002	Units 1 and 2 Entry into Limiting Condition for Operation 3.0.3 due to Main Control Room Ventilation Envelope Low Pressure
05000458/LER-2006-002	Loss of Safety Function of High Pressure Core Spray Due to Manual Deactivation
05000458/LER-2006-005	Automatic Start of Standby Service Water During Realignment of Reactor Plant Cooling Water	10 CFR 50.73(a)(2)(iv), System Actuation
05000461/LER-2006-002	Turbine Bypass Function Lost Due to Circuit Card Maintenance Frequency
05000461/LER-2006-003	High Reactor Water Level Scram Result of Bad Inverter Circuit Board Solder Joint	10 CFR 50.73(a)(2)(iv)(A), System Actuation
05000483/LER-2006-003	Unexpected Inoperability of the Emergency Exhaust System due to Inoperable Pressure Boundary	10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

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